Nuclear reactors -- Safety measures

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• Nuclear reactors
• Nuclear engineering -- Safety measures
• Nuclear facilities -- Safety measures
• Nuclear energy -- Safety measures
• Safety measures

• Nuclear reactors -- Safety measures -- Computer programs
• Nuclear reactors -- Safety measures -- Congresses
• Nuclear reactors -- Safety measures -- Data processing
• Nuclear reactors -- Safety measures -- Evaluation
• Nuclear reactors -- Safety measures -- History
• Nuclear reactors -- Safety measures -- International cooperation
• Nuclear reactors -- Safety measures -- Periodicals
• Nuclear reactors -- Safety measures -- Research
• Nuclear reactors -- Safety measures -- Testing
• Boiling water reactors -- Safety measures
• Breeder reactors -- Safety measures
• Engineering test reactors -- Safety measures
• Fast reactors -- Safety measures
• Gas cooled reactors -- Safety measures
• LOFT (Nuclear reactor safety test facility)
• Light water reactors -- Safety measures
• Materials testing reactors -- Safety measures
• Nuclear fuels -- Safety measures
• Nuclear pressure vessels -- Safety measures
• Organic cooled reactors -- Safety measures
• Pressurized water reactors -- Safety measures
• Water cooled reactors -- Safety measures
• Nuclear reactors -- Cores -- Safety measures
• Nuclear reactors -- Cuba -- Safety measures
• Nuclear reactors -- Former Soviet republics -- Safety measures
• Nuclear reactors -- Georgia -- Safety measures
• Nuclear reactors -- Michigan -- Safety measures
• Nuclear reactors -- North Carolina -- Safety measures
• Nuclear reactors -- Outer space -- Safety measures
• Nuclear reactors -- South Carolina -- Safety measures
• Nuclear reactors -- Soviet Union -- Safety measures
• Nuclear reactors -- Sweden -- Safety measures
• Nuclear reactors -- United States -- Safety measures
• Nuclear reactors -- Washington (State) -- Hanford -- Safety measures

• Nuclear reactor safety : hearings before the Joint Committee on Atomic Energy, Congress of the United States, Ninety-third Congress, ... . (Washington : U.S. Govt. Print. Off., 1974-), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust)
• 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 .... (Washington : U.S. Govt. Print. Off., 1976), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust)
• An analysis of U.S. nuclear health and safety information dissemination to selected foreign countries / prepared by F. Kertesz, B. Carroll, R. Kernohan, Franklin Research Center ; prepared for Office of International Programs, U.S. Nuclear Regulatory Commission. (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by François Kertész (page images at HathiTrust)
• Report of the Bulletins and Orders Task Force. (Washington, D.C. : Division of Project Management, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980), by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force (page images at HathiTrust)
• Safety analysis of nuclear concrete containment structures / prepared by P. Petrina, R. Sexsmith, R.N. White, Department of Structural Engineering, Cornell University ; prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1979), by P. Petrina (page images at HathiTrust)
• Bubble behavior in LMFBR core disruptive accidents : annual report October, 1977-September, 1978 / C. A. Erdman ... [et al.] ; prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. (Washington, D.C. : The Commission ; Springfield, Va. : Available from National Technical Information Service, 1979) (page images at HathiTrust)
• Bubble behavior in LMFBR core disruptive accidents : annual report, July 1, 1976 - September 30, 1977 / principal investigators, C.A. Erdman, A.B. Reynolds ; other contributors, M. Pilch ... [et al.], University of Virginia, Dept. of Nuclear Engineering and Engineering Services. (Washington, D.C.: Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commision ; Springfield, Va. : [for sale by the] National Technical Information Service, 1978) (page images at HathiTrust)
• Bubble behavior in LMFBR core disruptive accidents : annual report, October 1979 - September 1980 / prepared by A.B. Reynolds ... [et al.], Dept. of Nuclear Engineering and Engineering Physics, University of Virginia. (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981) (page images at HathiTrust)
• Downcomer effects in a 1/15-scale PWR geometry - experimental data report / C.J. Crowley, J.A. Block, C.N. Cary, CREARE, Inc. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1977), by Christopher J. Crowley (page images at HathiTrust)
• Safety evaluation report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, in the matter of Westinghouse Electric Corporation Reference Safety Analysis Report, RESAR-414, Docket no. STN 50-572. (Washington : Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation ; Springfield, Va. : for sale by the National Technical Information Service, 1978), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (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 / G.T. Hahn ... [et al.], Battelle-Columbus Laboratories. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ; Springfield, Va. : [for sale by the] National Technical Information Service, 1978) (page images at HathiTrust)
• Analysis of experiments on stainless steel flux welds / prepared by G. Wilkowski ... [et al.], Battelle's Columbus Division. (Washington, D.C. : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987) (page images at HathiTrust)
• An assessment of circumferentially complex-cracked pipe subjected to bending / prepared by G. Kramer, V. Papaspyropoulos, Battelle's Columbus Division. (Washington, D.C. : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by G. Kramer (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 / G.T. Hahn and others, Battelle Columbus Laboratories. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service, 1978) (page images at HathiTrust)
• Short term safety assessment on the environmental qualification of safety-related electrical equipment of SEP operating reactors. (Washington : The Commission, 1978) (page images at HathiTrust)
• Silver-indium-cadmium control rod behavior and aerosol formation in severe reactor accidents / David A. Petti, EG&G Idaho, Inc. (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by D. A. Petti (page images at HathiTrust)
• The possibility of local detonations during degraded-core accidents in the Bellefonte Nuclear Power Plant / M.P. Sherman and M. Berman. (Washington, D.C. : The Commission, 1987), by Martin P. Sherman (page images at HathiTrust)
• The effects of temperature, moisture, concentration, pressure, and mass transfer on the adsorption of krypton and xenon on activated carbon / D.W. Underhill, D.W. Moeller. (Washington, D.C. : Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Commission ; Springfield, Va. : National Technical Information Service, 1980), by D. W. Underhill (page images at HathiTrust)
• Special safeguards study : scopes of work. (Washington, D.C : United States Nuclear Regulatory Commission, Office of Special Studies, [1975]), by U.S. Nuclear Regulatory Commission. Office of Special Studies (page images at HathiTrust)
• Structure and drafting of safeguards regulatory documents / R. J. Cole ... [et al.] (Washington, D.C. : The Commission, 1997) (page images at HathiTrust)
• User's manual for RELAP3B-MOD 101 : a reactor system transient code. ([Washington, D.C.] : Division of System Safety, Office of Nuclear Reactor Regulation, Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service, [1976]) (page images at HathiTrust)
• "Reactor Pressure Vessel" Priority Program 22 NiMoCr 37 : "mechanism of deformation and of fracture (VBM)" : technical report. (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1977-) (page images at HathiTrust)
• Quarterly progress report on the Nuclear Safety Research Reactor (NSRR) experiments (1), October 1975 - March 1976 / Japan Atomic Research Institute, Division of Reactor Safety ; translated by Techtran Corporation. (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1978), by Nihon Genshiryoku Kenkyūjo (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 / G.T. Hahn ... [et al.], Battelle Columbus Laboratories. (page images at HathiTrust)
• Fracture evaluation of surface cracks embedded in reactor vessel cladding : unirradiated bend specimen results / prepared by D.E. McCabe, Materials Engineering Associates, Inc. (Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by D. E. McCabe (page images at HathiTrust)
• Nuclear health and safety : environmental, health, and safety practices at naval reactors facilities : report to the Chairman, Environment, Energy, and Natural Resources Subcommittee, Committee on Government Operations, House of Representatives / United States General Accounting Office. ([Washington, D.C.] : The Office, 1991), by United States General Accounting Office (page images at HathiTrust)
• Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - June 1979 / prepared by A.R. Rosenfield ... [et al.], Battelle Columbus Laboratories. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.: Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1979) (page images at HathiTrust)
• Experimental and analytical assessment of circumferentially surface-cracked pipes under bending / prepared by P.M. Scott and J. Ahmad, Battelle's Columbus Division. (Washington, D.C. : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by P. Scott (page images at HathiTrust)
• Strength and stiffness of reinforced concrete panels subjected to membrane shear, two-way and four-way reinforcing / prepared by C.H. Conley, R.N. White, P. Gergely, Department of Structural Engineering, Cornell University. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by C. H. Conley (page images at HathiTrust)
• Argonne low power reactor health physics manual / by E.D. Graham and P.G. Stoddart. (Argonne, Ill. : Argonne National Laboratory, 1959), by E. D. Graham (page images at HathiTrust)
• Hazard summary report for the Argonne AGN-201 reactor / by K.C. Ruzich and W.J. Sturm. (Argonne, Ill. : Argonne National Laboratory, 1962), by K. C. Ruzich (page images at HathiTrust)
• Some calculations pertaining to fast reactor safety / by D.M. ©ƯO Shea, D. Okrent, and J.M. Chaumont. (Lemont, III. : Argonne National Laboratory, 1962), by D. M. ©ƯO Shea (page images at HathiTrust)
• Measurements of light transmittance through thick shielding windows / by T.W. Eckels. (Argonne, Ill. : Argonne National Laboratory, 1960), by T. W. Eckels (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. (Washington : 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)
• Risk assessment Review Group report to the U.S. Nuclear Regulatory Commission / H. W. Lewis, Chairman. (Washington : U.S. Nuclear Regulatory Commission ; Springfield, Va. : available from National Technical Information Service, 1978) (page images at HathiTrust)
• Nuclear reactor safety : January 1-March 31, 1981 / compiled by Michael G. Stevenson [and] John C. Vigil, Los Alamos National Laboratory, Q (Energy) Division. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ; Los Alamos, N.M. : Los Alamos National Laboratory, 1981), by Michael G. Stevenson (page images at HathiTrust)
• Modeling of pool swell dynamics : progress report, March 1977 / W. G. Anderson, P. W. Huber, A. A. Sonin, Department of Mechanical Engineering, Massachusetts Institute of Technology. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service, 1977), by W. G. Anderson (page images at HathiTrust)
• Technical report on operating experience with boiling water reactor offgas systems / R. Lo ... [et al.]. (Washington, D.C. : Division of Operating Reactors, Office of Nuclear Reactor Regulation, Nuclear Regulatory Commission ; Springfield, Va. : for sale by the National Technical Information Service, 1978) (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 / prepared by A.R. Rosenfield ... [et al.], Battelle Columbus Laboratories. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.: Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980) (page images at HathiTrust)
• Plan for experimental characterization of clad vessel steel after irradiation / prepared by D.E. McCabe, Materials Engineering Associates. (Washington, D.C. : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by D. E. McCabe (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 / I. B. Wall ... [et al.] (Washington : The Commission, 1977), contrib. by Tenn.) International Conference of Nuclear Systems Reliability Engineering and Risk Assessment (1977 : Gatlinburg (page images at HathiTrust)
• LMFBR aerosol release and transport program : quarterly progress report for January-March 1980 / T.S. Kress [and] M.L. Tobias, Engineering Technology Division, Oak Ridge National Laboratory, operated by Union Carbide Corporation for the Department of Energy. (Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1980), by T. S. Kress (page images at HathiTrust)
• Observations on the reactor safety study a report / prepared by the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs of the U.S. House of Representatives, Ninety-fifth Congress, first session. (Washington : 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 (WASH-1400) : a review of the final report / U.S. Environmental Protection Agency, Office of Radiation Programs (Washington, D.C. : The Office, [1976?]), by United States. Environmental Protection Agency. Office of Radiation Programs (page images at HathiTrust)
• Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - March 1980 / prepared by A.R. Rosenfield ... [et al.], Battelle Columbus Laboratories. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.: Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980) (page images at HathiTrust)
• Design charts for a class of nonlinear systems with gaps under a variety of dynamic loads / prepared by J.C. Anderson and others, University of Southern California. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1979) (page images at HathiTrust)
• Safety analysis report for the Super Kukla prompt burst reactor / W.S. Gilbet, F.A. Kloverstrom, and F. Rienecker, Jr. (Livermore, Ca. : Lawrence Radiation Laboratory, 1964), by W. S. Gilbert (page images at HathiTrust)
• Plutonium recycle test reactor final safeguards analysis. N.G. Wittenbrock. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by N. G. Wittenbrock (page images at HathiTrust)
• Plutonium recycle test reactor final safeguards analysis. Staff of Reactor Engineering Development Operation, edited by N.G. Wittenbrock. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by Hanford Atomic Products Operation. Reactor Engineering Development Operation (page images at HathiTrust)
• Evaluation of chlorine inhibition of graphite oxidation as a gas-cooled reactor safeguard / R.E. Dahl. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by R. E. Dahl (page images at HathiTrust)
• Dynamics of the homogeneous reactor test / Paul R. Kasten. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by Paul R. Kasten (page images at HathiTrust)
• The multi-decade simulation of the Plutonium Recycle Program Critical Facililty / G.R. Taylor. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by G. R. Taylor (page images at HathiTrust)
• The analysis of plutonium-241 in urine / J. Donald Ludwick. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by J. Donald Ludwick (page images at HathiTrust)
• Decontamination of the ORNL thorex pilot plant / K.H. McCorkle, W.R. Winsbro. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by K. H. McCorkle (page images at HathiTrust)
• A Method for the disposal of volatile fission products from an accident in the Oak Ridge research reactor / F.T. Binford, T.H.J. Burnett. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by F. T. Binford (page images at HathiTrust)
• Remote control of the LITR / J.A. Cox, L.C. Oakes, W.H. Tabor. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by J. A. Cox (page images at HathiTrust)
• Administrative control of a research reactor / J.A. Cox. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by J. A. Cox (page images at HathiTrust)
• Operational safety of the homogenous reactor test / P.R. Kasten. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by P. R. Kasten (page images at HathiTrust)
• A philosophy oc control-system design / E.P. Epler. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by E. P. Epler (page images at HathiTrust)
• Containment problems in aqueous homogenous reactor systems / S.E. Beall. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by S. E. Beall (page images at HathiTrust)
• A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors / J.A. Lane ... [et al.]. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1959) (page images at HathiTrust)
• Critical experiments and nuclear safety at Oak Ridge National Laboratory / A.D. Callihan. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by A. D. Callihan (page images at HathiTrust)
• Standard operating procedure for the pool critical assembly / E.B. Johnson. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by E. B. Johnson (page images at HathiTrust)
• Operational safety of the ORNL graphite reactor using enriched-uranium fuel / P.R. Kasten, S. Jaye, M.P. Lietzke. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by P. R. Kasten (page images at HathiTrust)
• Safeguard report for a stainless steel research reactor for the BSF (BSR-II) / E.G. Silver, J. Lewin. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1958), by E. G. Silver (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 ... . (Washington : U.S. Govt. Print. Off., 1974-), by United States. Congress. Joint Committee on Atomic Energy (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. (Washington : 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. (Washington : 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)
• Bibliography on nuclear reactor fuel reprocessing and waste disposal / T.F. Connolly. ([Oak Ridge] United States Atomic Energy Commission, Division of Technical Information, [1960?]), by T. F. Connolly (page images at HathiTrust)
• Final safeguards report to the U. S. Atomic Energy Commission for the Cornell University TRIGA reactor. (Ithaca, Cornell University, Nuclear Reactor Laboratory, 1961), by David D. Clark (page images at HathiTrust)
• Reactor safety and oscillator tests. ([Detroit, Atomic Power Development Associates], 1956), by Hans A. Bethe (page images at HathiTrust)
• Safety analysis report : SNAPTRAN 2/10A-3 water immersion tests / edited by F.L. Bentzen, J.M. Waage. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by F. L. Bentzen (page images at HathiTrust)
• The advanced reactivity measurement facilities : a description and performance evaluation / by E.E. Burdick, E. Fast, D.W. Knight. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by Earl E. Burdick (page images at HathiTrust)
• Shutdown reactivity by the modified rod drop method / K.V. Moore. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by K. V. Moore (page images at HathiTrust)
• Spert I destructive test series : environmental monitoring and research studies / by D. F. Bunch. ([Idaho Falls, Idaho] : Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by D. F. Bunch (page images at HathiTrust)
• Dynamic pressure measurement devices in nuclear reactors / by P.H. Hofhine. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by P. H. Hofhine (page images at HathiTrust)
• Experimental organic cooled reactor : safety analysis report. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1962?]) (page images at HathiTrust)
• Feasibility and conceptual design for the step loss of coolant facility / by T.R. Wilson, O.M. Hauge, and G.B. Matheney. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by T. R. Wilson (page images at HathiTrust)
• SPERT II hazards summary report / by G.O. Bright and J.E. Grund. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1959]), by G. O. Bright (page images at HathiTrust)
• Transient tests of the BSR-II core in the SPERT I facility / L.A. Stephan. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by L. A. Stephan (page images at HathiTrust)
• Contributions to two problems in space-independent, nuclear-reactor dynamics. by A.A. Wasserman. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by Arthur Allen Wasserman (page images at HathiTrust)
• SPERT I destructive test program safety analysis report / by A.H. Spano and R.W. Miller. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by A. H. Spano (page images at HathiTrust)
• The reaction of metals with water and oxidizing gases at high temperatures / H. M. Higgins and R. D. Schultz. (Oak Ridge, Tenn., : U.S. Atomic Energy Commision, Technical Information Service Extension, 1957), by H. M. Higgins (page images at HathiTrust)
• Proceedings of the 1960 Idaho conference on reactor kinetics / edited by J.C. Haire and G.O. Bright. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by Idaho Conference on Reactor Kinetics (page images at HathiTrust)
• Kinetic studies on the SPERT I reactor. L.I. Deverall and G.W. Griffing. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1957]), by L. I. Deverall (page images at HathiTrust)
• Thermal stability of gadolinium nitrate solution at high temperature / by J.F. Koenig. (Idaho Falls, Idaho : U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by John Franklin Koenig (page images at HathiTrust)
• A survey of the Materials Testing Reactor shield / E. Fast, J.P. Byrom, J.W. McCaslin. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1953), by E. Fast (page images at HathiTrust)
• History and operating practices of the MTR Reactor Safeguard Committee / by D.R. deBoisblanc. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1956), by D. R. DeBoisblanc (page images at HathiTrust)
• Kinetic studies on the Spert I reactor. G.W. Griffing, L.I. Deverall. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1958]), by George W. Griffing (page images at HathiTrust)
• SPERT IV hazards summary report / F.L. Bentzen, J.G. Crocker. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1961]), by F. L. Bentzen (page images at HathiTrust)
• A standard practices guide for hazard analysis of experimental systems / by R.J. Nertney. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1958]), by R. J. Nertney (page images at HathiTrust)
• ETR core hydraulics / R.G. Beck, E.S. Brown, J.H. Rainwater. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1958]), by R. G. Beck (page images at HathiTrust)
• Shielding requirements for experiments ANL 2 and KAPL 2 / H.L. McMurry. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1952), by H. L. McMurry (page images at HathiTrust)
• Minimum risk specification limits / by F.H. Tingey and J.A. Merrill. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by Fred H. Tingey (page images at HathiTrust)
• SPERT III hazards summary report / by F. Schroeder. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1958]), by F. Schroeder (page images at HathiTrust)
• Metal-water reactions : rates of reaction of aluminum and aluminum-uranium alloys with water vapor at elevated temperatures / by W.F. Zelezny. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by W. F. Zelezny (page images at HathiTrust)
• A method of determining the intermediate energy neutron dose / by Dale E. Hankins. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1961]), by Dale E. Hankins (page images at HathiTrust)
• Nuclear nonproliferation and safety : concerns with the International Atomic Energy Agency's technical cooperation program : report to Congressional requesters / United States General Accounting Office. (Washington, D.C. (P.O. Box 37050, Washington, D.C. 20013) : The Office, [1997]), by United States General Accounting Office (page images at HathiTrust)
• Proceedings of the U.S. Nuclear Regulatory Commission Meeting on Reactor Vessel Liquid Level Measurement : held at National Bureau of Standards, Gaithersburg, Md., October 30, 1980 / edited by N.N. Kondic. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by U.S. Nuclear Regulatory Commission. Meeting on Reactor Vessel Liquid Level Measurement (page images at HathiTrust)
• Parametric study of a frangible-tube energy-absorption system for protection of a nuclear aircraft reactor / Richard L. Puthoff and Klaus H. Gumto. (Washington, D.C. : National Aeronautics and Space Administration ; [For sale by the Clearinghouse for Federal Scientific and Technical Information, Springfield, Virginia 22151], 1970), by Richard L. Puthoff (page images at HathiTrust)
• Failure of cobalt-60 radiation sources / J.I. Wagner and J.S. Milau. (Upton, N.Y. : Brookhaven National Laboratory, 1968), by J. I. Wagner (page images at HathiTrust)
• Diffusion of iodine through aluminum / A.W. Castleman, F.E. Hoffmann, and A.M. Eshaya. (Upton, N.Y. : Brookhaven National Laboratory, 1960), by A. W. Castleman (page images at HathiTrust)
• The determination of power and temperature overshoot in the reactor flash problem / K.T. Spinney. (Upton, N.Y. : Brookhaven National Laboratory, 1956), by K. T. Spinney (page images at HathiTrust)
• Instability in the Spert-I reactor : preliminary report / report prepared by S.G. Forbes, F. Schroeder, and W.E. Nyer. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1956]), by S. G. Forbes (page images at HathiTrust)
• Safety consideration in aqueous reprocesing plant operations / by W.G. Morrison. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by W. G. Morrison (page images at HathiTrust)
• Poor management of a nuclear light water reactor safety project, Energy Research and Development Administration, Nuclear Regulatory Commission / by the Comptroller General of the United States. (Washington : U.S. General Accounting Office, [1976]), by United States General Accounting Office (page images at HathiTrust)
• The Tower Shielding Facility safeguard report / by the Tower Shielding Facility Group, assisted by the Instrumentation and Controls Division, the Health Physics Division, and the Engineering Division. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1953), by Oak Ridge National Laboratory (page images at HathiTrust)
• A two-dimensional fluid finite element : final report / Department of Mechanical Engineering, Massachusetts Institute of Technology. (Washington, D.C. : Division of Project Management, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service, 1978), by Massachusetts Institute of Technology. Department of Mechanical Engineering (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 / prepared by a panel of the National Academy of Public Administration. ([Washington] : U.S. Nuclear Regulatory Commission, 1980), by National Academy of Public Administration (page images at HathiTrust)

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