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Nuclear reactors -- Outer space -- Safety measures

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Filed under: Nuclear reactors -- Outer space -- Safety measures

Computer study of emergency shutdowns of a 60-kilowatt reactor Brayton space power system (National Aeronautics and Space Administration ;, 1974), by Roy C. Tew, Kent S. Jefferies, and Lewis Research Center (page images at HathiTrust)

Items below (if any) are from related and broader terms.

Filed under: Nuclear reactors -- Outer space

Evaluation of tantalum-alloy-clad uranium mononitride fuel specimens from 7500-hour, 1040 ̊C pumped-lithium-loop test (National Aeronautics and Space Administration ;, 1974), by Gordon K. Watson and Lewis Research Center (page images at HathiTrust)

Filed under: Nuclear reactors -- Outer space -- Computer simulation

Digital computer study of nuclear reactor thermal transients during startup of 60-kWe Brayton power conversion system (National Aeronautics and Space Administration ;, 1974), by Kent S. Jefferies, Roy C. Tew, and Lewis Research Center (page images at HathiTrust)

Filed under: Nuclear reactors -- Outer space -- Control

Compatibility of refractory materials for nuclear reactor poison control systems (National Aeronautics and Space Administration ;, 1974), by John H. Sinclair and Lewis Research Center (page images at HathiTrust)

Filed under: Nuclear reactors -- Outer space -- Design and construction

Development concept for a small, split-core, heat-pipe-cooled nuclear reactor (National Aeronautics and Space Administration ;, 1974), by Edward Lantz, George F. Niederauer, Roland Breitwieser, and Lewis Research Center (page images at HathiTrust)

Filed under: Nuclear reactors -- Outer space -- Materials

Thermal-expansion method for lining tantalum alloy tubing with tungsten (National Aeronautics and Space Administration ;, 1973), by Gordon K. Watson, William F. Mattson, J. Daniel Whittenberger, and Lewis Research Center (page images at HathiTrust)

Filed under: Nuclear reactors -- Outer space -- Materials -- Effect of temperature on

Off-design temperature effects on nuclear fuel pins for an advanced space-power-reactor concept (National Aeronautics and Space Administration ;, 1974), by Kenneth J. Bowles and Lewis Research Center (page images at HathiTrust)

Filed under: Nuclear reactors -- Outer space -- Materials -- Testing

Compatibility of refractory materials for nuclear reactor poison control systems (National Aeronautics and Space Administration ;, 1974), by John H. Sinclair and Lewis Research Center (page images at HathiTrust)
Electrical heating tests of uranium dioxide external fuel configuration at emitter temperature of 1900 K (National Aeronautics and Space Administration ;, 1974), by Dominic C. DiIanni, John T. Mayer, and Lewis Research Center (page images at HathiTrust)
Compatibility tests of materials for a lithium-cooled space power reactor concept (National Aeronautics and Space Administration ;, 1973), by John H. Sinclair and Lewis Research Center (page images at HathiTrust)

Filed under: Nuclear reactors -- Materials -- Thermal properties -- Outer space

Materials technology programs in support of a mercury rankine space power system (National Aeronautics and Space Administration ;, 1973), by Phillip L. Stone and Lewis Research Center (page images at HathiTrust)

Filed under: Nuclear reactors -- Safety measures

Investigation of charges relating to nuclear reactor safety : hearings before the Joint Committee on Atomic Energy, Congress of the United States, Ninety-fourth Congress, second session .... (U.S. Govt. Print. Off., 1976), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust)
Nuclear reactor safety. Hearings before the Joint Committee on Atomic Energy, Congress of the United States, Ninety-third Congress, first session ... . (U.S. Govt. Print. Off., 1974), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust)
Major alternatives for government policies, organizational structures, and actions in civilian nuclear reactor emergency management in the United States : report to M. Rogovin for the NRC Three Mile Island Special Inquiry (U.S. Nuclear Regulatory Commission, 1980), by National Academy of Public Administration (page images at HathiTrust)
Siting of nuclear power reactors; discussion and comments on safety considerations. (New York, 1959), by Atomic Industrial Forum (page images at HathiTrust)
Reactor safeguards (Pergamon Press, 1962), by Charles Roberts Russell (page images at HathiTrust)
Nuclear exports, international safety and environmental issues : hearings before the Subcommittee on International Economic Policy and Trade of the Committee on Foreign Affairs, House of Representatives, Ninety-sixth Congress, December 18, 1979, and May 7, 1980. (U.S. Govt. Print. Off., 1980), by United State House Subcommittee on International Economic Policy and Trade (page images at HathiTrust)
Reactor safety study (Rasmussen report) oversight hearing before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-fourth Congress, second session ... June 11, 1976. (U.S. Govt. Print. Off., 1976), by United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment (page images at HathiTrust)
Nuclear reactor security against sabotage oversight hearing before the Subcommittee on Energy and the Environment, of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-fifth Congress, first session ... May 5, 1977. (U.S. Govt. Print. Off., 1977), by United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment (page images at HathiTrust)
Observations on the reactor safety study a report (U.S. Govt. Print. Off., 1977), by United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment (page images at HathiTrust)
Reactor safety study review oversight hearing before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-sixth Congress, first session ... February 26, 1979. (U.S. Govt. Print. Off., 1979), by United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment (page images at HathiTrust)
Safety evaluation report related to the preliminary design of the Standard Reference System, RESAR - 414. (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation ;, 1978), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (page images at HathiTrust)
Safety evaluation report related to construction of Erie Nuclear Plant, units 1 and 2, Ohio Edison Company, et al. Supplement no. 1 ([Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 1978., 1978), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, Pennsylvania Power Company, Duquesne Light Company, Cleveland Electric Illuminating Company, Toledo Edison Company, and Ohio Edison Company (page images at HathiTrust)
Anticipated transients without scram for light water reactors : staff report. (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Systems Safety ;, 1978), by United States Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
Technical report on operating experience with boiling water reactor offgas systems (Division of Operating Reactors, Office of Nuclear Reactor Regulation, Nuclear Regulatory Commission ;, 1978), by Ronnie Lo and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
An analysis of U.S. nuclear health and safety information dissemination to selected foreign countries (The Commission :, 1981), by François Kertész, R. H. Kernohan, B. Carroll, Franklin Research Center, and U.S. Nuclear Regulatory Commission. Office of International and State Programs (page images at HathiTrust)
Report of the Bulletins and Orders Task Force. (Division of Project Management, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission :, 1980), by U.S. Nuclear Regulatory Commission. Bulletins and Orders Task Force and U.S. Nuclear Regulatory Commission. Division of Project Management (page images at HathiTrust)
Safety analysis of nuclear concrete containment structures (The Commission :, 1979), by P. Petrina, Robert N. White, Robert G. Sexsmith, Cornell University. Department of Structural Engineering, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Risk assessment Review Group report to the U.S. Nuclear Regulatory Commission (U.S. Nuclear Regulatory Commission ;, 1978), by H. W. Lewis and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
Bubble behavior in LMFBR core disruptive accidents : annual report October, 1977-September, 1978 (The Commission ;, 1979), by C. A. Erdman, University of Virginia. Department of Nuclear Engineering and Engineering Physics, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Bubble behavior in LMFBR core disruptive accidents : annual report, July 1, 1976 - September 30, 1977 (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commision ;, 1978), by Albert B. Reynolds, C. A. Erdman, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and University of Virginia. Department of Nuclear Engineering (page images at HathiTrust)
Bubble behavior in LMFBR core disruptive accidents : annual report, October 1979 - September 1980 (Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1981), by Albert B. Reynolds, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and University of Virginia. Department of Nuclear Engineering and Engineering Physics (page images at HathiTrust)
Downcomer effects in a 1/15-scale PWR geometry - experimental data report (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1977), by Christopher J. Crowley, C. N. Cary, J. A. Block, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and inc Creare (page images at HathiTrust)
Design charts for a class of nonlinear systems with gaps under a variety of dynamic loads (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1979), by J. C. Anderson, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and University of Southern California (page images at HathiTrust)
Strength and stiffness of reinforced concrete panels subjected to membrane shear, two-way and four-way reinforcing (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1981), by C. H. Conley, Peter Gergely, Richard N. White, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Cornell University. Department of Structural Engineering (page images at HathiTrust)
Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : third annual progress report, October 1976 - September 1977 (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ;, 1978), by G. T. Hahn, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, June-December 1979 (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.:, 1980), by Alan R. Rosenfield, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
Analysis of experiments on stainless steel flux welds (Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by G. M. Wilkowski, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
Experimental and analytical assessment of circumferentially surface-cracked pipes under bending (Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by P. Scott, J. Ahmad, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
An assessment of circumferentially complex-cracked pipe subjected to bending (Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by G. Kramer, V. Papaspyropoulos, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : quarterly report, January - March 1977 (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ;, 1978), by G. T. Hahn, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
Short term safety assessment on the environmental qualification of safety-related electrical equipment of SEP operating reactors. (The Commission, 1978), by U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
A two-dimensional fluid finite element : final report (Division of Project Management, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission ;, 1978), by Massachusetts Institute of Technology. Department of Mechanical Engineering and U.S. Nuclear Regulatory Commission. Division of Project Management (page images at HathiTrust)
Silver indium cadmium control rod behavior and aerosol formation in severe reactor accidents. (Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by D. A. Petti, Idaho National Engineering Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and EG & G Idaho (page images at HathiTrust)
The possibility of local detonations during degraded-core accidents in the Bellefonte Nuclear Power Plant (The Commission, 1987), by Martin P. Sherman, M. Berman, U.S. Nuclear Regulatory Commission. Division of Reactor System Safety, and Sandia National Laboratories. Reactor Safety Research Dept (page images at HathiTrust)
The effects of temperature, moisture, concentration, pressure, and mass transfer on the adsorption of krypton and xenon on activated carbon (Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission :, 1980), by D. W. Underhill, D. W. Moeller, and U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards (page images at HathiTrust)
Special safeguards study : scopes of work. (United States Nuclear Regulatory Commission, Office of Special Studies, 1975), by U.S. Nuclear Regulatory Commission. Office of Special Studies (page images at HathiTrust)
Overview of the reactor safety study consequence model : paper presented at the International Conference of Nuclear Systems Reliablity Engineering and Risk Assessment held at Gatlinburg, Tennessee, June 19-25, 1977 (The Commission, 1977), by I. B. Wall, Sandia Laboratories, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Branch, and Tenn.) International Conference of Nuclear Systems Reliability Engineering and Risk Assessment (1977 : Gatlinburg (page images at HathiTrust)
User's manual for RELAP3B-MOD 101 : a reactor system transient code. (Division of System Safety, Office of Nuclear Reactor Regulation, Nuclear Regulatory Commission ;, 1976), by U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
Quarterly progress report on the Nuclear Safety Research Reactor (NSRR) experiments (1), October 1975 - March 1976 (U.S. Nuclear Regulatory Commission, 1978), by Nihon Genshiryoku Kenkyūjo and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : 4th annual report, October 1977 - October 1978 (1979), by G. T. Hahn, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
LMFBR aerosol release and transport program : quarterly progress report for January-March 1980 (U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1980), by T. S. Kress, M. L. Tobias, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, and Oak Ridge National Laboratory. Engineering Technology Division (page images at HathiTrust)
Nuclear reactor safety : January 1-March 31, 1981 (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ;, 1981), by Michael G. Stevenson, John C. Vigil, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Los Alamos National Laboratory. Q (Energy) Division (page images at HathiTrust)
Nuclear reactor safety hearings before the Joint Committee on Atomic Energy, Congress of the United States, Ninety-third Congress, first session ... . (U.S. Govt. Print. Off., 1975), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust)
Fracture evaluation of surface cracks embedded in reactor vessel cladding : unirradiated bend specimen results (Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by D. E. McCabe, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering, and Materials Engineering Associates (page images at HathiTrust)
Plan for experimental characterization of clad vessel steel after irradiation (Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by D. E. McCabe, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety, and Materials Engineering Associates (page images at HathiTrust)
Modeling of pool swell dynamics : progress report, March 1977 (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ;, 1977), by W. G. Anderson, A. A. Sonin, P. W. Huber, U.S. Nuclear Regulatory Commission, and Massachusetts Institute of Technology. Department of Mechanical Engineering (page images at HathiTrust)
"Reactor Pressure Vessel" Priority Program 22 NiMoCr 37 : "mechanism of deformation and of fracture (VBM)" : technical report. (U.S. Nuclear Regulatory Commission, 1977), by H. Dietmann, U.S. Nuclear Regulatory Commission, and Staatliche Materialprüfungsanstalt (Germany) (page images at HathiTrust)
Environmental, health, and safety practices at naval reactors facilities (The Office, 1991), by United States General Accounting Office (page images at HathiTrust)
Argonne low power reactor health physics manual (Argonne National Laboratory, 1959), by E. D. Graham, P. G. Stoddart, U.S. Atomic Energy Commission, and Argonne National Laboratory. Idaho Division (page images at HathiTrust)
Measurements of light transmittance through thick shielding windows (Argonne National Laboratory, 1960), by T. W. Eckels, U.S. Atomic Energy Commission, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust)
Hazard summary report for the Argonne AGN-201 reactor (Argonne National Laboratory, 1962), by K. C. Ruzich, W. J. Sturm, U.S. Atomic Energy Commission, Argonne National Laboratory, and International Institute of Nuclear Science and Engineering (page images at HathiTrust)
Some calculations pertaining to fast reactor safety (Argonne National Laboratory, 1962), by D. M. ©ƯO Shea, J. M. Chaumont, D. Okrent, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety study (WASH-1400) : a review of the final report (The Office, 1976), by United States. Environmental Protection Agency. Office of Radiation Programs, Inc Intermountain Technologies, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
Radiological surveillance studies at a pressurized water nuclear power reactor (United States Environmental Protection Agency, Radiochemistry and Nuclear Engineering Branch, National Environmental Research Center ;, 1973), by B. Kahn and United States. Environmental Protection Agency. Radiochemistry and Nuclear Engineering Branch (page images at HathiTrust; US access only)
Safety analysis report for the Super Kukla prompt burst reactor (Lawrence Radiation Laboratory, 1964), by W. S. Gilbert, F. Rienecker, F. A. Kloverstrom, and Lawrence Radiation Laboratory (page images at HathiTrust)
Revised report of the reactor hazards for the physical constants testing reactor (Hanford Atomic Products Operation, 1962), by H. L. Henry, E. C. Watson, P. F. Nichols, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Physics and Instruments Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
The multi-decade simulation of the Plutonium Recycle Program Critical Facililty (U.S. Atomic Energy Commission, 1961), by Doc Taylor, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Physics and Instrument Research and Development Operation (page images at HathiTrust)
Evaluation of chlorine inhibition of graphite oxidation as a gas-cooled reactor safeguard (U.S. Atomic Energy Commission, 1961), by R. E. Dahl, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
The analysis of plutonium-241 in urine (U.S. Atomic Energy Commission, 1960), by J. Donald Ludwick, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
Plutonium recycle test reactor final safeguards analysis. Supplement 3, Effluent activity limits (U.S. Atomic Energy Commission, 1961), by N. G. Wittenbrock, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
Plutonium recycle test reactor final safeguards analysis. Supplement 1, Additional studies (U.S. Atomic Energy Commission, 1960), by Hanford Atomic Products Operation. Reactor Engineering Development Operation, N. G. Wittenbrock, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, and Hanford Works (page images at HathiTrust)
Nuclear safety program semiannual progress report for period ending (Oak Ridge National Laboratory, 1965), by Oak Ridge National Laboratory and U.S. Atomic Energy Commission (page images at HathiTrust)
The Tower Shielding Facility safeguard report (Oak Ridge National Laboratory, 1953), by Oak Ridge National Laboratory, L. S. Abbott, and U.S. Atomic Energy Commission (page images at HathiTrust)
A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors (Oak Ridge National Laboratory, 1959), by J. A. Lane, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Reactor Systems Evaluation Department (page images at HathiTrust)
Standard operating procedure for the pool critical assembly (Oak Ridge National Laboratory, 1960), by E. B. Johnson, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Neutron Physics Division (page images at HathiTrust)
Safeguard report for a stainless steel research reactor for the BSF (BSR-II) (Oak Ridge National Laboratory, 1958), by Ernest Gerard Silver, J. Lewin, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Neutron Physics Division (page images at HathiTrust)
Operational safety of the ORNL graphite reactor using enriched-uranium fuel (Oak Ridge National Laboratory, 1960), by P. R. Kasten, M. P. Lietzke, S. Jaye, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Reactor Experimental Engineering Division (page images at HathiTrust)
Decontamination of the ORNL thorex pilot plant (Oak Ridge National Laboratory, 1956), by K. H. McCorkle, W. R. Winsbro, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
Dynamics of the homogeneous reactor test (Oak Ridge National Laboratory, 1956), by Paul R. Kasten, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Reactor Experimental Engineering Division (page images at HathiTrust)
Administrative control of a research reactor (Oak Ridge National Laboratory, 1956), by J. A. Cox, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Operations Division (page images at HathiTrust)
A Method for the disposal of volatile fission products from an accident in the Oak Ridge research reactor (Oak Ridge National Laboratory, 1956), by F. T. Binford, T. H. J. Burnett, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory (page images at HathiTrust)
Critical experiments and nuclear safety at Oak Ridge National Laboratory (Oak Ridge National Laboratory, 1956), by A. D. Callihan, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Applied Nuclear Physics Division (page images at HathiTrust)
Operational safety of the homogenous reactor test (Oak Ridge National Laboratory, 1956), by P. R. Kasten, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Reactor Experimental Engineering Division (page images at HathiTrust)
A philosophy oc control-system design (Oak Ridge National Laboratory, 1956), by E. P. Epler, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Instrumentation and Controls Division (page images at HathiTrust)
Containment problems in aqueous homogenous reactor systems (Oak Ridge National Laboratory, 1956), by S. E. Beall, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Reactor Experimental Engineering Division (page images at HathiTrust)
Remote control of the LITR (Oak Ridge National Laboratory, 1956), by J. A. Cox, W. H. Tabor, L. C. Oakes, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Operations Division (page images at HathiTrust)
Final safeguards report to the U. S. Atomic Energy Commission for the Cornell University TRIGA reactor. (Cornell University, Nuclear Reactor Laboratory, 1961), by David D. Clark and Cornell University. Nuclear Reactor Laboratory (page images at HathiTrust)
Program summary for the Civilian Reactor Development Program (The Deputy Assistant Secretary ;, 1982), by United States. Department of Energy. Office of the Deputy Assistant Secretary for Breeder Reactor Programs and United States. Department of Energy. Deputy Assistant Secretary for Nuclear Reactor Programs (page images at HathiTrust)
Reactor safety and oscillator tests. (Atomic Power Development Associates], 1956), by Hans A. Bethe (page images at HathiTrust)
The reaction of metals with water and oxidizing gases at high temperatures (U.S. Atomic Energy Commision, Technical Information Service Extension, 1957), by H. M. Higgins, R. D. Schultz, and Aerojet-General Corporation (page images at HathiTrust)
Spert I destructive test series : environmental monitoring and research studies (Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by D. F. Bunch and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
SPERT II hazards summary report (U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by G. O. Bright, J. E. Grund, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
A standard practices guide for hazard analysis of experimental systems (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by R. J. Nertney and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Safety analysis report : SNAPTRAN 2/10A-3 water immersion tests (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by F. L. Bentzen, J. M. Waage, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Dynamic pressure measurement devices in nuclear reactors (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by P. H. Hofhine, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
The advanced reactivity measurement facilities : a description and performance evaluation (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by Earl E. Burdick, D. W. Knight, E. Fast, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
Shutdown reactivity by the modified rod drop method (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by K. V. Moore, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Engineering test reactor core hydraulics (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by R. G. Beck, J. H. Rainwater, E. S. Brown, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Shielding requirements for experiments ANL 2 and KAPL 2 (U.S. Atomic Energy Commission, Technical Information Service, 1952), by H. L. McMurry and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
A survey of the Materials Testing Reactor shield (U.S. Atomic Energy Commission, Technical Information Service, 1953), by E. Fast, J. W. McCaslin, J. P. Byrom, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
History and operating practices of the MTR Reactor Safeguard Committee (U.S. Atomic Energy Commission, Idaho Operations Office, 1956), by D. R. DeBoisblanc and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Minimum risk specification limits (U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by Fred H. Tingey, J. A. Merrill, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Kinetic studies on the Spert I reactor. [Part] I, Initial behavior by the energy model (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by George W. Griffing, L. I. Deverall, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
On the initial shutdown of the Spert I reactor for periods greater than 50 milliseconds (U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by L. I. Deverall, George W. Griffing, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
SPERT III hazards summary report (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by F. Schroeder and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Experimental organic cooled reactor : safety analysis report. (U.S. Atomic Energy Commission, Idaho Operations Office, in the 1960s), by Idaho National Reactor Testing Station and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Calculation and measurement of the reactor describing function (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by Arthur Allen Wasserman, U.S. Atomic Energy Commission, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
Transient tests of the BSR-II core in the SPERT I facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by L. A. Stephan, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
SPERT I destructive test program safety analysis report (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by A. H. Spano, R. W. Miller, Idaho National Reactor Testing Station, U.S. Atomic Energy Commission, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Feasibility and conceptual design for the step loss of coolant facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by T. R. Wilson, G. B. Matheney, O. M. Hauge, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Metal-water reactions : rates of reaction of aluminum and aluminum-uranium alloys with water vapor at elevated temperatures (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by W. F. Zelezny, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
A method of determining the intermediate energy neutron dose (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by Dale E. Hankins, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
Thermal stability of gadolinium nitrate solution at high temperature (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by John Franklin Koenig, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
Special Power Excursion Reactor Tests IV hazards summary report (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by F. L. Bentzen, J. G. Crocker, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
Poor management of a nuclear light water reactor safety project, Energy Research and Development Administration, Nuclear Regulatory Commission (U.S. General Accounting Office, 1976), by United States General Accounting Office (page images at HathiTrust)
Nuclear nonproliferation and safety : concerns with the International Atomic Energy Agency's technical cooperation program : report to Congressional requesters (The Office, 1997), by United States General Accounting Office (page images at HathiTrust)
Analysis of temperature-dependent neutron transmission and self-indication measurements on tantalum at 2-keV neutron energy (National Aeronautics and Space Administration ;, 1973), by Thor T. Semler and Lewis Research Center (page images at HathiTrust)
NASA TN D-5730 (National Aeronautics and Space Administration ; [For sale by the Clearinghouse for Federal Scientific and Technical Information, Springfield, Virginia 22151], 1970), by Richard L. Puthoff, Klaus H. Gumto, Lewis Research Center, and United States National Aeronautics and Space Administration (page images at HathiTrust)
Failure of cobalt-60 radiation sources (Brookhaven National Laboratory, 1968), by J. I. Wagner, J. S. Milau, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Diffusion of iodine through aluminum (Brookhaven National Laboratory, 1960), by A. W. Castleman, A. M. Eshaya, F. E. Hoffmann, U.S. Atomic Energy Commission, Brookhaven National Laboratory, and Inc Associated Universities (page images at HathiTrust)
The determination of power and temperature overshoot in the reactor flash problem (Brookhaven National Laboratory, 1956), by K. T. Spinney, Inc Associated Universities, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
Operations Division. (U.S. Atomic Energy Commission, Idaho Operations Office, 1956), by S. G. Forbes, Warren E. Nyer, F. Schroeder, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
Idaho Chemical Processing Plant, Process Development Branch.. (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by W. G. Morrison, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Analysis for large fast critical assemblies (ZPR-6 and ZPR-9) (Argonne National Laboratory, Reactor Physics Division, 1966), by G. K. Rusch, R. A. Karam, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Physics Division (page images at HathiTrust)
Safety analysis of a nominal 3700-liter UO2 core in the ZPR-6 and -9 facility (Argonne National Laboratory, Reactor Physics Division, 1968), by G. K. Rusch, R. A. Karam, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Physics Division (page images at HathiTrust)
The subroutine used to calculate design basis accidents for the ZPR-6 and -9 plutonium safety analysis report (ANL-7442) (Argonne National Laboratory, Reactor Physics Division, 1968), by G. K. Rusch, J. M. Van Doorninck, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Physics Division (page images at HathiTrust)
Safety problems of liquid-metal-cooled fast breeder reactors (Argonne National Laboratory; distributed by National Technical Information Service, 1970), by C. N. Kelber, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
Nuclear reactor hazards summary review (Hanford Atomic Products Operation, 1964), by B. B. Lane, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Nuclear safety study of Nuclear fuel processing in 333 building (Hanford Atomic Products Operation, 1964), by C. L. Brown, J. E. Ruffin, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Nuclear-reactor department disaster plan for 100-N area (Hanford Atomic Products Operation, 1964), by J. R. Bolliger, F. Cox, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Plutonium recycle test reactor operating safety limits (Hanford Atomic Products Operation, 1964), by Leland Jerome Nitteberg, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Production reactor nuclear safety audit and inspection system : N-reactor department (Hanford Atomic Products Operation, 1964), by R. E. Trumble, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Plutonium recycle critical facility operating safety limits (Hanford Atomic Products Operation, 1964), by F. Swanberg, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Physical constants testing reactor operating satety limits (Hanford Atomic Products Operation, 1964), by F. Swanberg, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Establishment of reliability of important reactor safety systems (Hanford Atomic Products Operation, 1964), by M. C. Leverett, R. E. Trumble, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
100-N equipment experience report : 20-50 percent design power level (Hanford Atomic Products Operation, 1964), by J. W. Helton, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Review of 300 area emergency plans (Hanford Atomic Products Operation, 1964), by C. L. Brown, R. L. Junkins, K. R. Heid, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Engineering audit of N-reactor's emergency cooling water system (Hanford Atomic Products Operation, 1964), by H. G. Johnson, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Composition and decontamination of residual water-boiler off-gas (Los Alamos Scientific Laboratory of the University of California, 1953), by Harold M. Busey, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Ultra high temperature reactor experiment (UHTREX) hazard report (Los Alamos Scientific Laboratory of the University of California, 1962), by U.S. Atomic Energy Commission and Los Alamos Scientific Laboratory. K-Division (page images at HathiTrust)
Source measurement : determining the release from a point source by remotely located samplers (Los Alamos Scientific Laboratory of the University of California, 1964), by Richard W. Henderson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor minimum critical dimensions (Los Alamos Scientific Laboratory of the University of California, 1965), by Carroll B. Mills, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Ultra high temperature reactor critical experiment (UCX) safety analysis report (Los Alamos Scientific Laboratory of the University of California, 1965), by U.S. Atomic Energy Commission and Los Alamos Scientific Laboratory. K-Division (page images at HathiTrust)
Reactor Technology Division. (Oak Ridge National Laboratory, 1950), by C. P. Coughlen, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
The high flux isotope reactor accident analysis (Oak Ridge National Laboratory, 1967), by F. T. Binford, Eugene N. Cramer, T. E. Cole, Oak Ridge National Laboratory, Union Carbide Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Analysis of scale-up in the U. S. nuclear safety program (Oak Ridge National Laboratory, 1966), by C. E. Miller, W. E. Browning, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Annual progress report on studies in applied solid mechanics (Oak Ridge National Laboratory., 1970), by Oak Ridge National Laboratory, W. L. Greenstreet, U.S. Atomic Energy Commission, and Union Carbide Corporation (page images at HathiTrust)
Labor policy in atomic energy plants : hearings before the Joint Committee on Atomic Energy, Congress of the United States, Eightieth Congress, second session. Part 1, March 9, 10, 12, 15, and 16, 1948. (U.S. G.P.O., 1948), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust)
Health and safety considerations for uranium fuel fabrication facilities (U.S. Atomic Energy Commission, Technical Information Service Extension, 1958), by William A. Brobst, U.S. Atomic Energy Commission. Chicago Operations Office, and U.S. Atomic Energy Commission (page images at HathiTrust)
Hazards summary report on the zero power experiments for the army package power reactor (Technical Information Service Extension, 1956), by J. L. Meem, J. W. Noaks, U.S. Atomic Energy Commission, and Alco Products (Firm) (page images at HathiTrust)
Safety of HRT (United States Atomic Energy Commission, Technical Information Service ;, 1955), by Paul R. Kasten, V. K. Par©Øe, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Homogeneous Reactor Test cooler design data (United States Atomic Energy Commission, Technical Information Service ;, 1955), by E. D. Arnold, A. T. Gresky, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
HRT safety calculations (United States Atomic Energy Commission, Technical Information Service Extension, 1955), by Paul R. Kasten, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Containment of fragments from runaway reactor (Stanford Research Institute, 1958), by N. R. Zabel, Stanford Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Addendum to the SPERT III hazards summary report : low-enrichment oxide core (U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by J. E. Houghtaling, J. C. Haire, J. A. Norbert, Idaho National Reactor Testing Station, U.S. Atomic Energy Commission. Idaho Operations Office, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Interim report on Scoping Emergency Cooling Heat Transfer Series I and II (U.S. Atomic Energy Commission, Idaho Operations Office, 1968), by L. G. Schlenker, W. S. Little, C. M. Moser, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
Hazards evaluation for the Los Alamos critical assembly facility (Los Alamos Scientific Laboratory of the University of California, 1962), by Hugh Campbell Paxton, John D. Orndoff, P. G. Koontz, W. U. Geer, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
A comparison of the neutron dose rates obtained with the single-sphere instrument, multisphere method, and Hurst proportional counter / (Los Alamos Scientific Laboratory of the University of California, 1964), by Dale E. Hankins, Raymond A. Pederson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Respirator drying cabinet (Los Alamos Scientific Laboratory of the University of California, 1964), by Earl J. Cox, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Shock impingement experiments on crushable solids / by P. Lieberman. (Armour Research Foundation, Illinois Institute of Technology, 1959), by P. Lieberman, U.S. Atomic Energy Commission, and Armour Research Foundation (U.S.) (page images at HathiTrust; US access only)
Accidental dispersion of reactor poisons and the controlled distance required (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, 1958), by R. L. Menegus, H. F. Ring, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust; US access only)
A continuous monitor for airborne plutonium (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1956), by Dowdey C. Collins, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
Poison retention in reactor fuses (General Electric, Atomic Products Division, 1957), by R. J. Spera, S. N. Stilwell, U.S. Atomic Energy Commission, and General Electric Company. Aircraft Nuclear Propulsion Department (page images at HathiTrust)
Shielding computer program 11-0, reactor shield analysis (General Electric, Aircraft Nuclear Propulsion Dept., Atomic Products Division, 1958), by K.B. Hanchon and General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division (page images at HathiTrust)
Test data from the 2 (pi) solid-angle shield-cover experiment (General Electric, Aircraft Nuclear Propulsion Dept., Atomic Products Division, 1958), by R. F. Rohrer, W. L. Weiss, R. F. Brenton, J. G. Carver, R. H. Clark, General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
SPERT I fuse trigger tests. (General Electric, Aircraft Nuclear Propulsion Dept., Atomic Products Division, 1959), by R. F. Spera, S. N. Stilwell, R. L. Waterfield, and General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division (page images at HathiTrust)
Summary hazards evaluation of the SMR facility (General Electric, Aircraft Nuclear Propulsion Dept., 1959), by J. D. Simpson, United States Air Force, U.S. Atomic Energy Commission, and General Electric Company. Aircraft Nuclear Propulsion Department (page images at HathiTrust)
Magnetic automatic power-range control for an aircraft nuclear reactor (General Electric, Aircraft Nuclear Propulsion Dept., 1961), by P. C. Sharr, J. L. Scharf, S. F. Hemmenway, J. A. Russell, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
Aircraft nuclear propulsion department nuclear safety guide (General Electric, Nuclear Materials and Propulsion Operation., 1961), by William A. Pryor, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
The DASA-TRIGA Mark F pulsing reactor facility (Technical Services, Department of Commerce ;, 1961), by C.E. Clifford, G.B. West, R.H. Stahl, M. S. Nelkin, U.S. Atomic Energy Commission, and General Dynamics Corporation. General Atomic Division (page images at HathiTrust)
An electronic trip system for reactor protection : model D (Knolls Atomic Power Laboratory, General Electric Company, 1956), by E. J. Wade, D. S. Davidson, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
Governmental Indemnity and Reactor Safety : hearings before the United States Joint Committee on Atomic Energy, Eighty- Fifth Congress, first session, on Mar. 25-27, 1957. (U.S. G.P.O., 1957), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust)
Safety evaluation report (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation ;, 1977), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (page images at HathiTrust)
Nuclear reactors and earthquakes (U.S. Atomic Energy Commission ;, 1963), by U.S. Atomic Energy Commission, Inc Holmes & Narver, and Lockheed Aircraft Corporation (page images at HathiTrust)
Research and development in reactor safety; a program of the United States Atomic Energy Commission. ([Washington, 1959), by B. John Garrick and U.S. Atomic Energy Commission (page images at HathiTrust)
A nuclearly safe 12-1/4-in. I.D. packed liquid entrainment separator (Oak Ridge, Tennessee : Union Carbide Corporation, 1963., 1963), by H. F. Henry, C.E. Newlon, H.F. Henry, U.S. Atomic Energy Commission, and Union Carbide Corporation (page images at HathiTrust)
A test cell for evaluating the air leakage of building components (Atomics International, 1960), by L. Baurmash, F.W. Schlapp, C. T. Nelson, R. L. Koontz, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Physics measurements on the SNAP experimental reactor (SER) (Atomics International, 1961), by F. H. Clark, M. V. Davis, S. G. Wogulis, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety progress report (Atomics International ;, in the 20th century), by U.S. Atomic Energy Commission. Technical Information Center and North American Aviation. Atomics International Division (page images at HathiTrust)
Thermal transient behavior of the neutron sensor of a reactor safety device (Atomics International, 1958), by S. H. Fitch, T. H. Springer, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Safety device tests in Special Power Excursion Reactor Test-I (Atomics International, 1958), by Stephen H. Fitch, Thomas H. Springer, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Differential pressure safety device (Atomics International, 1959), by R. Holland, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
A study of reactor hazards (Los Angeles, California : North American Aviation, Inc., 1949., 1949), by Mark M. Mills, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Aerospace safety program Systems Nuclear Auxiliary Power 10A reentry flight demonstration (RFD-1) analysis of flight-test data. (Canoga Park, California : Atomics International, 1964., 1964), by R. D. Elliott, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Behavior of Systems Nuclear Auxiliary Power 10A during orbital reentry. (Washington, D.C. : Office of Technical Services, 1964., 1964), by D. K. Nelson, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Atomics International Reactor Safety Program a digital simulator for power reactor dynamics. (Canoga Park, California : Atomics International, 1964., 1964), by R.A. Blaine, R.F. Berland, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Standard safety analysis report : (GESSAR) General Electric Company (U.S. Atomic Energy Commission, Technical Information Center, 1974), by Faye H. Horn, U.S. Atomic Energy Commission. Advisory Committee on Reactor Safeguards, and U.S. Atomic Energy Commission. Technical Information Center (page images at HathiTrust)
A study of research reactor operating and safety experience (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Branch, 1962., 1964), by B. John Garrick, B. Shimizu, R. H. Karcher, J. M. Duncan, Willard C. Gekler, U.S. Atomic Energy Commission, and Holmes & Narver (page images at HathiTrust)
A high-pressure Bp10sFb3s loading system for a reactor safety element (Atomics International, 1957), by Charles R.F. Smith, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Electrical analog application to a reactor safety device program (Atomics International, 1957), by Charles C. Weeks, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Development of the Organic Moderated Reactor Experiment control--safety rod (Atomics International, 1957), by H. Strahl, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Heat flow in the trigger of a reactor safety device (Atomics International, 1958), by Thomas H. Springer, Norman C. Miller, U.S. Atomic Energy Commission. Technical Information Center, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Hanford safety device summary report (Atomics International, 1958), by Stephen H. Fitch, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust; US access only)
A high vacuum application of inflatable seals for the processing refabrication experiment (Atomics International, 1959), by J. L. Ballif, W. K. Mock, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Coupled diaphragm safety device for power reactors (Atomics International, 1959), by L. E. Johnson, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Pressure and temperature instrumentation for dynamic measurements in the Kinetic Experiments on Water Boilers Program : a summary report (Atomics International, 1960), by Sigmund P. Harris, Carle F. Bumpus, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety device reliability determination using sequential analysis (Atomics International, 1960), by S. H. Fitch, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
ADEP, one- and two-dimensional few-group kinetics code (Columbus, Ohio : Battelle, Columbus Laboratories, 1971., 1971), by Richard S. Denning, U.S. Atomic Energy Commission, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
Reactor containment (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1963., 1963), by Richard J. Smith, American Society of Civil Engineers, and U.S. Atomic Energy Commission. Technical Information Service Extension (page images at HathiTrust)
BONUS (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by Puerto Rico Electric Power Authority, U.S. Atomic Energy Commission, and General Nuclear Engineering Corporation (page images at HathiTrust)
Annual summary report - 1959. Kinetic studies of heterogeneous water reactors. (Los Angeles, California : Ramo-Wooldridge Division, Research Laboratory ; Washington, D.C. : Available from the Office of Technical Services, Department of Commerce, 1960., 1960), by U.S. Atomic Energy Commission, TRW Inc, and Ramo-Wooldridge Corporation (page images at HathiTrust)
Annual summary report - 1960. Kinetic studies of heterogeneous water reactors. (TRW inc, Ramo-Wooldridge Division, 1960), by U.S. Atomic Energy Commission and TRW Inc (page images at HathiTrust)
Containment of fragments from runaway reactor (Washington, D.C. : Office of Technical Services, Department of Commerce, 1958., 1958), by N. R. Zabel, Stanford Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Containment of fragments from runaway reactor. (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by G. B. Huber, N. R. Zabel, Stanford Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Containment of fragments from runaway reactor. (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by G.B. Huber, N.R. Zabel, M.P. Stallybrass, D.D. Keough, Stanford Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Containment of fragments from a runaway reactor. (Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by G. B. Huber, N. R. Zabel, Stanford Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Containment of fragments from a runaway reactor. (Washington, D.C. : Office of Technical Services, Department of Commerce, 36., 1960), by G. B. Huber, N. R. Zabel, Stanford Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Containment of fragments from a runaway reactor. (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by R. W. White, N. B. Botsford, Stanford Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Containment of fragments from a runaway reactor : final report (Washington, D.C. : Office of Technical Services, Department of Commerce, 1964., 1964), by R. W. Gates, Stanford Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Criticality : a bibliography of unclassified literature (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Division of Technical Information, 1961., 1961), by R. L. Scott and U.S. Atomic Energy Commission (page images at HathiTrust)
Reports on reactor safety (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service Extension, 1956., 1956), by Hugh Ellison Voress and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety : a literature search (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, [1959], 1959), by Richard J. Smith and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety : a literature search (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, [1959], 1959), by Richard J. Smith and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety : a literature search (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, [1960], 1960), by Richard J. Smith and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety : a literature search (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, [1961], 1961), by Richard J. Smith and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety : a literature search (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Division of Technical Information Extension, 1962., 1962), by Richard J. Smith and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety : A literature search ([Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Division of Technical Information, 1963., 1963), by Richard J. Smith and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety : A literature search ([Oak Ridge, Tennessee, U.S. Atomic Energy Commission, Division of Technical Information, 1964., 1964), by Richard J. Smith and U.S. Atomic Energy Commission (page images at HathiTrust)
United States Atomic Energy Commission, Division of Reactor Development presents an information meeting on the Fast Reactor Program to be held at Chicago, Illinois, November 20-21, 1957 (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1957., 1957), by U.S. Atomic Energy Commission. Division of Reactor Development (page images at HathiTrust)
Scavenging of radioactive particulate matter and aerosols in connection with nuclear reactor operation : final summary report (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1962., 1962), by Jan Rosiński, U.S. Atomic Energy Commission, and Armour Research Foundation (U.S.) (page images at HathiTrust)
Kinetic studies of heterogeneous water reactors : Annual summary report 1961. (TRW Space Technology Laboratories, 1961), by TRW Space Technology Laboratories and U.S. Atomic Energy Commission (page images at HathiTrust; US access only)
Kinetic studies of heterogeneous water reactors : Annual summary report 1962. (TRW Space Technology Laboratories, 1962), by TRW Space Technology Laboratories and U.S. Atomic Energy Commission (page images at HathiTrust; US access only)
Kinetic studies of heterogeneous water reactors : Annual summary report 1963. (TRW Space Technology Laboratories, 1963), by TRW Space Technology Laboratories and U.S. Atomic Energy Commission (page images at HathiTrust; US access only)
Kinetic studies of heterogeneous water reactors : annual summary report 1964. (TRW Space Technology Laboratories, 1964), by TRW Space Technology Laboratories and U.S. Atomic Energy Commission (page images at HathiTrust; US access only)
Yankee Atomic Electric Company, research and development program (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Departtment ; Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1957., 1957), by William H. Arnold, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation. Atomic Power Division (page images at HathiTrust)
Technical report on anticipated transients without scram for water-cooled power reactors : September 1973. (U.S. Govt. Print. Off., 1973), by U.S. Atomic Energy Commission. Regulatory Staff (page images at HathiTrust)
AEC experimental program on reactor safety : a monograph (Industrial Information Branch, Technical Information Service, Atomic Energy Commission, 1956), by Richard H. Graham, D. Glenn Boyer, and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor safety and hazards evaluation ... course ... (Cincinnati, 1962), by United States. Public Health Service. Division of Radiological Health and Robert A. Taft Sanitary Engineering Center (page images at HathiTrust)
An investigation of strain-energy absorption potential as the criterion for determining optimum reactor-vessel containment design (The Laboratory, 1958), by Md.) Naval Ordnance Laboratory (White Oak (page images at HathiTrust)
Davis-Besse Nuclear Power Station : Toledo Edison Company (Operating-License Stage) (Oak Ridge, Tennessee : U.S. Energy Research and Development Administration, Technical Information Center, 1975., 1975), by Wanda H. Williams, U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards, and United States. Energy Research and Development Administration. Technical Information Center (page images at HathiTrust)
Davis-Besse Nuclear Power Station : Toledo Edison Company (Operating-License Stage) (U.S. Energy Research and Development Administration, Office of Public Affairs, Technical Information Center ;, 1976), by Wanda H. Williams, U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards, and United States. Energy Research and Development Administration. Technical Information Center (page images at HathiTrust)
Standard safety analysis report : (GESSAR-238) General Electric Company (U.S. Energy Research and Development Administration, Office of Public Affairs, Technical Information Center ;, 1976), by Patsy L. Hendricks, U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards, and United States. Energy Research and Development Administration. Technical Information Center (page images at HathiTrust)
Standard safety analysis report : (GESSAR-251) : General Electric Company (U.S. Energy Research and Development Administration, Office of Public Affairs, Technical Information Center ;, 1976), by Mickey M. Moore, U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards, United States. Energy Research and Development Administration. Office of Public Affairs, and United States. Energy Research and Development Administration. Technical Information Center (page images at HathiTrust)
Reference safety analysis report : (RESAR-3S) : Westinghouse Electric Corporation (U.S. Energy Research and Development Administration, Office of Public Affairs, Technical Information Center ;, 1976), by Patsy L. Hendricks, U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards, United States. Energy Research and Development Administration. Office of Public Affairs, and United States. Energy Research and Development Administration. Technical Information Center (page images at HathiTrust)
Safety device test in Kinetic Experiments on Water Boilers I (Canoga Park, California : Atomics International, [1958], 1958), by Charles C. Weeks, Stephen H. Fitch, U.S. Atomic Energy Commission, and North American Aviation. Atomics International Division (page images at HathiTrust)
Graphical presentation of the activities from pile-irradiated uranium (Downey, California : Atomic Energy Research Department, North American Aviation, Inc., 1954., 1954), by R. L. Koontz, A. A. Jarrett, U.S. Atomic Energy Commission, and North American Aviation (page images at HathiTrust)
Three Mile Island Nuclear Station Unit 2. (Washington D.C. : U.S. Nuclear Regulatory Commission, 1978., 1978), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, Pennsylvania Electric Company, Jersey Central Power and Light Company, and Metropolitan Edison Company (page images at HathiTrust)
Safety evaluation report / docket nos STN 50-553 and STN 50-554. (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation ;, 1977), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (page images at HathiTrust)
Comments on the NRC safety research program budget. (Nuclear Regulatory Commission, Advisory Committee on Reactor Safeguards ;, 1979), by U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards (page images at HathiTrust)
A review of NRC regulatory processes and functions (Washington : Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 1980., 1980), by U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards (page images at HathiTrust)
Guideline for the development of a methodology for measuring level of effectiveness of physical protection facilities at fixed-site facilities (Division of Safeguards, Fuel Cycle and Environmental Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1978), by Wolf Haberman and Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards (page images at HathiTrust)
Comments on the NRC safety research program budget for fiscal year 1982. (Nuclear Regulatory Commission, Advisory Committee on Reactor Safeguards ;, 1980), by U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards (page images at HathiTrust)
Rasmussen report (N.R.C. ;, 1975), by U.S. Nuclear Regulatory Commission and U.S. Atomic Energy Commission (page images at HathiTrust)
Structure and drafting of safeguards regulatory documents (Washington : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Safeguards, Fuel Cycle, and Environmental Research ; Seattle, Wa. : Battelle Northwest Laboratories, 1977., 1977), by R. J. Cole, Pacific Northwest Laboratory, and Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards (page images at HathiTrust)
Comments on the Nuclear Regulatory Commission safety research program budget (Washington, D.C. : Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, in the 20th century), by U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards (page images at HathiTrust)
Preliminary hazards summary report Babcock & Wilcox test reactor. (Lynchburg, Va. ;, 1962), by Babcock & Wilcox Company. Atomic Energy Division (page images at HathiTrust; US access only)
Atomic energy, reactor safeguards : agreement between the United States of America and the Federal Republic of Germany : effected by exchange of letters signed at Washington November 5, 1981. (Dept. of State :, 1983), by Germany (West), United States. 1981 Nov. 5, and United States Department of State (page images at HathiTrust)
Safeguards aspects of reactor vessel design (Knolls Atomic Power Laboratory, General Electric Company, 1956), by W. E. Cooper, D. R. Miller, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
Criteria and methods for evaluating environmental reactor hazards (Knolls Atomic Power Laboratory, General Electric Company, 1956), by J. J. Fitzgerald, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
Atomic energy : technical information exchange and research and development on reactor safety, arrangement between the United States of America and the Federal Republic of Germany, signed at Washington March 6, 1974. (U.S. Dept. of State : for sale by the Supt. of Docs., U.S. Govt. Print. Off., 1976), by United States and United States Department of State (page images at HathiTrust)
Atomic energy : technical information exchange on light water reactor safety research, arrangement between the United States of America and France, signed at Washington and Paris September 23 and October 16, 1974. (Dept. of State : for sale by the Supt. of Docs., U.S. Govt. Print. Off., 1976), by United States and United States Department of State (page images at HathiTrust)
Atomic energy : reactor safety experiments : agreement between the United States of America and other governments, opened for signature January 24, 1975. (Dept. of State : for sale by the Supt. of Docs., U.S. Govt. Print. Off., 1977), by United States and United States Department of State (page images at HathiTrust)
Atomic energy : technical information exchange in reactor safety research and development : implementing agreement between the United States of America and other governments, done at Paris May 20, 1976. (Dept. of State : for sale by the Supt. of Docs., U.S. Govt. Print. Off., 1977), by United States and United States Department of State (page images at HathiTrust)
Atomic energy : reactor safety experiments : agreement between the United States of America and the United Kingdom of Great Britain and Northern Ireland, signed November 10 and December 14, 1976. (Dept. of State : for sale by the Supt. of Docs., U.S. Govt. Print. Off., 1977), by United States and United States Department of State (page images at HathiTrust)
Final environmental impact statement : safety research experiment facilities, Idaho National Engineering Laboratory, Idaho (Energy Research and Development Administration ;, 1977), by United States. Energy Research and Development Administration (page images at HathiTrust)
Reactor material debris formation scoping tests (Argonne, Illinois : Argonne National Laboratory, Reactor Analysis and Safety Division, 1988., 1988), by J. D. Gabor, B. W. Spencer, R. W. Aeschlimann, R. T. Purviance, University of Chicago, and Argonne National Laboratory (page images at HathiTrust)
Experimental and analytical studies of passive heat removal systems for advanced LMRs (Argonne, Illinois : Argonne National Laboratory, Reactor Engineering Division, 1991., 1991), by J. B. Heineman, J. H. Tessier, R. R. Stewart, D. R. Pedersen, P. A. Lottes, University of Chicago, and Argonne National Laboratory (page images at HathiTrust)
Reactor safety and oscillator tests ([Atomic Power Development Associates], 1956), by Hans A. Bethe, U.S. Atomic Energy Commission, and Inc Atomic Power Development Associates (page images at HathiTrust)
Calculation of air scattered gamma radiation escaping through a shield opening : application to the HRT (Oak Ridge, Tennessee : Oak Ridge National Laboratory, 1956., 1956), by H.C. Claiborne, T. B. Fowler, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Estimated gamma radiation levels at access holes in the HRT shielding (Oak Ridge, Tennessee : Oak Ridge National Laboratory, 1957., 1957), by C. W. Collins, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
The passive response of a metal fueled pool-type reactor to the chilled inlet accident (Argonne, Illinois : Argonne National Laboratory, Chemical Technology Division, 1993., 1993), by R. B. Vilim, University of Chicago, and Argonne National Laboratory (page images at HathiTrust)
Analysis of severe accident energetics in metallic-fueled, liquid metal cooled reactors (Argonne, Illinois : Argonne National Laboratory, Reactor Analysis Division, 1994., 1994), by E. E. Morris, A. M. Tentner, University of Chicago, and Argonne National Laboratory (page images at HathiTrust)
Atomic energy : reactor safety experiments : agreement between the United States of America and other governments, opened for signature April 14, 1977. (Dept. of State : for sale by the Supt. of Docs., U.S. Govt. Print. Off., 1979), by United States and United States Department of State (page images at HathiTrust)
Plutonium recycle test reactor final safeguards analysis (Hanford Atomic Products Operation, General Electric, 1959), by Hanford Atomic Products Operation. Reactor Engineering Development Operation, J. K. Anderson, P. C. Walkup, N. G. Wittenbrock, Oak Ridge National Laboratory, and Hanford Atomic Products Operation (page images at HathiTrust)
Chemical Engineering Division Research Highlights. : May 1963 - April 1964 (Argonne National Laboratory, Chemical Engineering Division, 1964), by R. C. Vogel and Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division summary report. : April, May, June, 1962 (Argonne National Laboratory, Chemical Engineering Division, 1962), by Stephen Lawroski and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1961 (Argonne National Laboratory, 1962), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division summary report. : October, November, December, 1961 (Argonne National Laboratory, Chemical Engineering Division, 1962), by Stephen Lawroski and Argonne National Laboratory (page images at HathiTrust)
Reactor Engineering Division, Quarterly report Section II : April, May, June, 1956. (Argonne National Laboratory, Reactor Engineering Division, 1956), by Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1964 (Argonne National Laboratory, 1965), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division Semiannual report. : January - June 1964 (Argonne National Laboratory, Chemical Engineering Division, 1964), by R. C. Vogel and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1962 (Argonne National Laboratory, 1963), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Safeguard report : Livermore pool type reactor (U.S. Atomic Energy Commission, Technical Information Service Extension, 1957), by Robert L. Detterman, U.S. Atomic Energy Commission, and Foster Wheeler Corporation (page images at HathiTrust)
Hazard evaluation report on the fast reactor zero power experiment (Zero Power Reactor III) (Argonne National Laboratory, 1961), by R. Rice, H. V. Lichtenberger, B. Cerutti, R. O. Brittan, M. Novick, F. W. Thalgott, R. L. McVean, and J. K. Long (page images at HathiTrust)
Hazard summary report on the Experimental Boiling Water Reactor (EBWR) (Argonne National Laboratory, 1958), by J. M. West and Argonne National Laboratory (page images at HathiTrust)
The effect of deionized water on reactor effluent activities. Part II, Zirconium and aluminum clad fuel (Hanford Atomic Products Operation, 1964), by W. B. Silker, C. W. Thomas, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
The Tower Shielding Facility safeguard report (Technical Information Service Extension, 1956), by L. S. Abbott, U.S. Atomic Energy Commission, Oak Ridge National Laboratory, and Carbide and Carbon Chemicals Corporation (page images at HathiTrust)
Final hazards summary report to the Advisory Committee on Reactor Safeguards on a research reactor for the Massachusetts Institute of Technology (Technical Information Service Extension, 1956), by Theos Jardin Thompson, Massachusetts Institute of Technology, and U.S. Atomic Energy Commission. Advisory Committee on Reactor Safeguards (page images at HathiTrust)
Interim report : FARET experimental program (Argonne National Laboratory, Reactor Engineering Division, 1963), by Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division summary report. : July, August, September, 1962 (Argonne National Laboratory, Chemical Engineering Division, 1962), by Stephen Lawroski and Argonne National Laboratory (page images at HathiTrust)
EBR-II dry critical experiments : Experimental program, experimental procedures, and safety considerations (Argonne National Laboratory, Reactor Engineering Division, 1961), by L. J. Koch and Argonne National Laboratory (page images at HathiTrust)
Hazards summary report on the oxide critical experiments (Argonne National Laboratory, Reactor Engineering Division, 1957), by W. C. Redman, L. R. Dates, J. A. Thie, and Argonne National Laboratory (page images at HathiTrust)
Design and hazards summary report Boiling Reactor Experiment V (BORAX V) (Argonne National Laboratory, 1961), by R. E. Rice and Argonne National Laboratory (page images at HathiTrust)
Transistorized trip circuit for critical assemblies (Knolls Atomic Power Laboratory, General Electric Company, 1958), by E. J. Wade, D. S. Davidson, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
Chemical Engineering Division summary report. : April, May, June, 1963 (Argonne National Laboratory, Chemical Engineering Division, 1963), by Stephen Lawroski and Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division summary report. : October, November, December, 1962 (Argonne National Laboratory, Chemical Engineering Division, 1963), by Stephen Lawroski and Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division summary report. : July, August, September, 1961 (Argonne National Laboratory, Chemical Engineering Division, 1961), by Stephen Lawroski and Argonne National Laboratory (page images at HathiTrust)
Initial testing and operation of the Argonne Low Power Reactor (ALPR) (Argonne National Laboratory, Reactor Engineering Division, 1959), by Eberhard E. Hamer and Argonne National Laboratory (page images at HathiTrust)
Summary report on the hazards of the Argonaut reactor (Argonne National Laboratory, Reactor Engineering Division, 1956), by D. H. Lennox, C. N. Kelber, and Argonne National Laboratory (page images at HathiTrust)
Plutonium recycle critical facility final safeguards analysis : supplements (Hanford Atomic Products Operation, 1964), by F. Swanberg, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
Plutonium recycle test reactor preliminary safeguards analysis (Hanford Atomic Products Operation ;, 1958), by N. G. Wittenbrock, General Electric Company, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
Hazards summary report for the Battelle research reactor (U.S. Atomic Energy Commission, Technical Information Service, 1955), by S. L. Fawcett, J. N. Anno, A. Klickman, R. F. Redmond, Joel W. Chastain, Battelle Memorial Institute, and U.S. Atomic Energy Commission. Advisory Committee on Reactor Safeguards (page images at HathiTrust)
Safety analysis report : snaptran 2/10A-1 safety tests (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by J. M. Waage, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
A method for beta-gamma hand and shoe counting under varying background conditions (Hanford Atomic Products Operation, 1963), by W. G. Spear, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
Addendum to the Spert IV hazards summary report : capsule driver core (Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by R. W. Miller, T. F. Lagier, Richard K. McCardell, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
Hazards summary report for the army package power reactor. (Technical Information Service Extension, 1955), by U.S. Atomic Energy Commission and Alco Products (Firm) (page images at HathiTrust)
Reactor Development Program Progress Report. : May 1965 (Argonne National Laboratory, 1965), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division Research Highlights. : May 1964 - April 1965 (Argonne National Laboratory, Chemical Engineering Division, 1965), by R. C. Vogel and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1963 (Argonne National Laboratory, 1964), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division Semiannual report. : July - December, 1963 (Argonne National Laboratory, Chemical Engineering Division, 1964), by Stephen Lawroski and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1960 (Argonne National Laboratory, 1961), by N. Hilberry and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : November 1964 (Argonne National Laboratory, 1964), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Chemical Engineering Division Research Highlights : May 1962 - April 1963 (Argonne National Laboratory, Chemical Engineering Division, 1963), by Stephen Lawroski and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : April 1963 (Argonne National Laboratory, 1963), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : March 1961 (Argonne National Laboratory, 1961), by N. Hilberry and Argonne National Laboratory (page images at HathiTrust)
Safety analysis report Argonne fast critical facility (ZPR-VI) (Argonne National Laboratory, Reactor Physics Division, 1963), by W. Y. Kato, L. R. Dates, G. J. Fischer, and Argonne National Laboratory (page images at HathiTrust)
Hazards evaluation report associated with the operation of EBWR at 100 MW (Argonne National Laboratory, 1959), by E. A. Wimunc, J. M. Harrer, and Argonne National Laboratory (page images at HathiTrust)
Plutonium recycle critical facility : final safeguards analysis (Hanford Atomic Products Operation, 1962), by J. K. Anderson, W. K. Winegardner, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
Kinetic studies of heterogeneous water reactors : annual summary report 1966. (Redondo Beach, California : TRW Systems Group, 1966., 1966), by TRW Systems Group and U.S. Atomic Energy Commission (page images at HathiTrust)
Filters, sorbents, and air cleaning systems as engineered safeguards in nuclear installations (Oak Ridge, Tennessee : Oak Ridge National Laboratory, Nuclear Safety Information Center, 1966., 1966), by G. W. Keilholtz, U.S. Atomic Energy Commission, Oak Ridge National Laboratory, and Nuclear Safety Information Center (page images at HathiTrust)
Design principles of reactor protection instrument systems (Oak Ridge, Tennessee : Oak Ridge National Laboratory, Nuclear Safety Information Center 1968., 1968), by S. H. Hanauer, C. S. Walker, U.S. Atomic Energy Commission, Nuclear Safety Information Center, and Oak Ridge National Laboratory (page images at HathiTrust)
Bubble behavior in LMFBR core disruptive accidents : annual report, July 1, 1976 - September 30, 1977 (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commision, 1978., 1978), by C. A. Erdman, Alan E. Waltar, P. L. Garner, M. F. Kennedy, M. Pilch, A. B. Reynolds, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Measurements and standards for nuclear materials safeguards, quarterly report. (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Safeguards, Fuel Cycle and Environmental Research ;, in the 20th century), by Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards (page images at HathiTrust)
Reactor safety research programs, quarterly progress report (The Division ;, in the 20th century), by U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research and Brookhaven National Laboratory. Department of Nuclear Energy (page images at HathiTrust)
Investigations of the seismological input to the safety design of nuclear power reactors in New England ([Washington, D.C.] : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, 1979., 1979), by M. A. Chinnery, Lincoln Laboratory, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : quarterly report, January - March 1978 (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1979., 1979), by G. T. Hahn, Alan R. Rosenfield, J. Lereim, C. Marschall, R. G. Hoagland, C. H. Popelar, P. C. Gehlen, M. W. Kanninen, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
Safeguards material control and accounting program quarterly report January-March 1979 (Washington, D. C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Virginia. : National Technical Information Service, 1980, 1980), by Arturo Maimoni, D. R. Dunn, Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards, and Lawrence Livermore Laboratory (page images at HathiTrust)
Size distribution of drops from containment spray nozzles (Washington, D.C. : Nuclear Regulatory Commission, 1979., 1979), by T. B. Powers, David Louis Reid, Pacific Northwest Laboratory, United States. Department of Energy, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
Examination of offsite radiological emergency protective measures for nuclear reactor accidents involving core melt (Albuquerque, New Mexico : Dept. of Energy, Sandia Laboratories, 1978., 1978), by David C. Aldrich, Norman C. Rasmussen, Peter E. McGrath, Massachusetts Institute of Technology, Sandia Laboratories, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
Reactor safety research programs : quarterly progress report, April 1-June 30, 1979 (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1978., 1979), by J. L. Hooper, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Reactor safety research programs : quarterly report, October-December 1979 (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1980., 1980), by C. W. Dotson, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Pacific Northwest Laboratory (page images at HathiTrust)
Advanced reactor safety research programs quarterly progress report <Apr. 1-June 30, 1979-> (Washington, D.C. : Reactor Safety Research Division, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, in the 1970s), by Brookhaven National Laboratory. Department of Nuclear Energy, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and U.S. Nuclear Regulatory Commission. Division of Advanced Reactor Safety Research (page images at HathiTrust)
Inspection methods for physical protection project : quarterly report, September-November 1980 (Washington, D. C. : U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, 1981., 1981), by D. D. Bowden, R. W. Thatcher, J. W. Savage, G. Rogue, A. W. Olson, C. Minichino, Lawrence Livermore Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
Inspection methods for physical protection project : quarterly report, June-August, 1980 (Washington, D. C. : U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; , 1980., 1980), by D. D. Bowden, R. W. Thatcher, J. W. Savage, F. Rogue, A. W. Olson, C. Minichino, R. T. Bradley, Lawrence Livermore Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
Reactor safety : a literature search (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Division of Technical Information, 1971., 1971), by Henry D. Raleigh and U.S. Atomic Energy Commission (page images at HathiTrust)
Introductory user's manual for the U.S. Nuclear Regulatory Commission Reactor Safety Research data bank (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1982., 1982), by Nora R. Scofield, E. T. Laats, Hershal A. Hardy, EG & G Idaho, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
Selected review and evaluation of U.S. safety research vis-a-vis foreign safety research for nuclear power plants (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983), by John D. Stevenson, F. A. Thomas, Stevenson & Associates, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
Seismic review of the Millstone I Nuclear Power Plant as part of the systematic evaluation program (Washington, D.C. : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1981., 1981), by T. A. Nelson, J. D. Stevenson, D. A. Wesley, C. Y. Liaw, Raymond C. Murray, United States. National Technical Information Service, United States Government Printing Office, Lawrence Livermore Laboratory, and U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (page images at HathiTrust)
Technology, safety and costs of decommissioning reference light water reactors following postulated accidents (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1982-, 1982), by E. S. Murphy, G. M. Holter, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
Reactor safety research quarterly report, July-September 1983 and October-December 1983, vol. 27 and 28 (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1984., 1984), by Sandia National Laboratories and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
Reactor safety research programs : quarterly report ... 1984 ([Washington, D.C.] : Nuclear Regulatory Commission [Office of Nuclear Regulatory Research], Division of Reactor Safety Research, [1984-1985], 1984), by Pacific Northwest Laboratory, S. K. Edler, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Reactor safety research quarterly report, April-June 1983, vol. 26 (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1984-, 1984), by Sandia National Laboratories and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
Reactor safety research quarterly report, January 1983, vol. 25 (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1984, 1984), by Sandia National Laboratories and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
Assessment of radiation effects relating to reactor pressure vessel cladding (Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1983., 1984), by W. R. Corwin, Oak Ridge National Laboratory. Metals and Ceramics Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
Acoustic emission monitoring of hot functional testing, Watts Bar Unit 1 Nuclear Reactor (Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1984., 1984), by P. H. Hutton, R. A. Pappas, J. C. Harris, M. A. Friesel, J. F. Dawson, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
Identification of equipment and components predicted as significant contributors to severe core damage (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1984., 1984), by Harry W. Heiselmann, EG & G Idaho, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
Reactor development program progress report December 1968 (Argonne, Illinois. : Argonne National Laboratory, 1969., 1969), by Robert B. Duffield, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
Chemical engineering division research highlights : May 1968 - December 1968 (Argonne, Ill. : Argonne National Laboratory, 19XX., 1969), by R. C. Vogel and Argonne National Laboratory (page images at HathiTrust)
An Early history of criticality safety (Los Alamos, New Mexico : Los Alamos Scientific Laboratory of the University of California, 1971., 1971), by Roy Reider, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
CMB-5 health and safety manual (Los Alamos, New Mexico : Los Alamos Scientific Laboratory of the University of California, 1972., 1972), by W. N. Miner, F. W. Schonfeld, D. L. Douglass, R. O. Elliott, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Nuclear reactor safety : quarterly progress report July 1-September 30, 1977 (Los Alamos, New Mexico : Los Alamos Scientific Laboratory of the University of California, 1978., 1978), by James F. Jackson, Michael G. Stevenson, United States. Depertment of Energy, Los Alamos Scientific Laboratory, U.S. Nuclear Regulatory Commission. Division of Systems Safety, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Nuclear reactor safety, quarterly progress report (Los Alamos Scientific Laboratory, in the 20th century), by Los Alamos Scientific Laboratory, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
The nuclear research reactor at the University of Michigan : a conceptual design of the facility; an evaluation of the hazards of operation and provisions for limiting these hazards (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, 1953., 1953), by William K. Luckow, Lawrence C. Widdoes, Russell B. Mesler, Michigan Memorial Phoenix Project, and U.S. Atomic Energy Commission (page images at HathiTrust)
Technical foundations of TRIGA. ([San Diego, California] : General Atomic, 1958., 1958), by General Dynamics Corporation. General Atomic Division, John Jay Hopkins Laboratory for pure and applied science, and General Atomic Company (page images at HathiTrust; US access only)
Manual of protective action guides and protective actions for nuclear incidents (U.S. Gov. Print. Off., 1979), by United States. Environmental Protection Agency. Office of Radiation Programs. Environmental Analysis Division (page images at HathiTrust)
Proceedings of the U.S. Nuclear Regulatory Commission Eighth Water Reactor Safety Research Information Meeting held at National Bureau of Standards, Gaithersburg, Maryland, October 27-31, 1980. (Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1982), by Water Reactor Safety Research Information Meeting (8th : 1980 : National Bureau of Standards) and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)

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