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Pressurized water reactors -- Design and construction

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• Pressurized water reactors
• Nuclear reactors -- Design and construction
• Water cooled reactors -- Design and construction
• Design and construction

• Pressurized water reactors -- Design and construction -- Indexes
• Pressurized water reactors -- Cores -- Design and construction
• Pressurized water reactors -- Oregon -- Design and construction

• Pressurized water reactor for production of steam (Argonne National Laboratory, 1959), by L.E. Link, C.F. Bullinger, R.R. Rhode, R. J. Gariboldi, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Comparison of Calder Hall and PWR reactor types (American Radiator and Standard Sanitary Corporation, 1957), by J. W. Webster, D. R. Mash, D. P. Herron, A. Puishes, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Pressurized water reactors fuel element specifications (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, [1957], 1957), by U.S. Atomic Energy Commission and Westinghouse Electric Corporation (page images at HathiTrust)
• Summary report on the hazards associated with the pressurized water reactor : flexible assembly (Washington, D.C. : Office of Technical Services, Department of Commerce, 1954., 1954), by H. A. Morewitz, J. J. Taylor, E. R. Sanford, Bettis Atomic Power Laboratory, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation (page images at HathiTrust)
• Investigation of a seeded PWR (Washington, D.C. : Office of Technical Services, Department of Commerce, 1955., 1955), by Bettis Atomic Power Laboratory, Westinghouse Electric Corporation. Atomic Power Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Study-by simulator techniques-of transient pressures in high pressure water systems utilizing a surge tank (Washington, D.C. : Office of Technical Services, Department of Commerce, 1955., 1955), by W. M. Gajewski, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• PWR vapor container design criteria. (Oak Ridge,Tennessee: U.S. Atomic Energy Commission, Technical Information Extension, 1954., 1954), by U.S. Atomic Energy Commission (page images at HathiTrust)
• Spectral shift control reactor design and economic study (Office of Technical Services, 1961), by D. Mars, D. Gans, U.S. Atomic Energy Commission, Stone and Webster Engineering Corporation, and Babcock & Wilcox Company (page images at HathiTrust)

• Pressurized water reactor reference nuclear power plant safety analysis report (SWESSAR-P1) : Stone & Webster Engineering Corporation (Oak Ridge, Tennessee: U.S. Energy Research and Development Administration, Office of Public Affairs, Technical Information Center, 1975., 1975), by Patsy L. Hendricks, U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards, United States. Energy Research and Development Administration. Technical Information Center, and Stone and Webster Engineering Corporation (page images at HathiTrust)
• Pressurized water reactor reference nuclear power plant safety analysis report (SWESSAR-P1) : Stone & Webster Engineering Corporation (Oak Ridge, Tennessee: U.S. Energy Research and Development Administration, Office of Public Affairs, Technical Information Center, 1976., 1976), by Patsy L. Hendricks, U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards, United States. Energy Research and Development Administration. Technical Information Center, and Stone and Webster Engineering Corporation (page images at HathiTrust)

• Pebble Springs Nuclear Plant : Units 1 and 2, Portland General Electric Company (Construction-Permit Stage) (Oak Ridge, Tennessee : U.S. Energy Research and Development Administration, Technical Information Center, 1975., 1975), 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)

• Saxton Plutonium Program semiannual progress report for the period ending December 31, 1966 (Pittsburg, Pennsylvania. : Westinghouse Electric Corporation, Nuclear Fuel Division, 1967., 1967), by R. S. Miller, U.S. Atomic Energy Commission. New York Operations Office, Westinghouse Electric Corporation. Nuclear Fuel Division, and Euratom (page images at HathiTrust)

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

• Tentative Structural Design Basis for Reactor Pressure Vessels and Directly Associated Components (Pressurized, Water Cooled Systems) (1 Dec 1958 revision), by United States Navy (page images at HathiTrust)
• SPERT III Thermowell Failure and Replacement (Idaho Falls, ID: U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by R. E. Heffner, Stephen Walter Gleave, and J. A. Norberg (page images at HathiTrust)
• The Shippingport pressurized water reactor (Addison-Wesley Pub. Co., 1958), by U.S. Atomic Energy Commission. Division of Reactor Development and Switzerland) United Nations International Conference on the Peaceful Uses of Atomic Energy (2nd : 1958 : Geneva (page images at HathiTrust)
• Final environmental statement related to selection of the preferred closed cycle cooling system at Indian Point Unit no. 3. (U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation :, 1979), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (page images at HathiTrust)
• Pipe cracking experience in light-water reactors (Division of Operating Reactors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission :, 1980), by L. Frank and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
• Staff report on the generic assessment of feedwater transients in pressurized water reactors designed by the Babcock & Wilcox Company (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation ;, 1979), by U.S. Nuclear Regulatory Commission. Division of Systems Safety, U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
• Pressurized water reactor lateral core response routine, FAMREC (Fuel Assembly Mechanical Response Code) (The Division :, 1979), by R. L. Grubb, EG & G Idaho, and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
• Overview and comparison of US commercial nuclear power plants. (Division of Systems Technology, Office of Nucler Reactor Regulation, U.S. Nuclear Regulatory Commission :, 1990), by Peter Lobner, C. Cavallin, C. Donahoe, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Technology, and Science Applications International Corporation (page images at HathiTrust)
• An assessment of the failure rate for the beltline region of PWR pressure vessels during normal operation and certain transient conditions (Division of Engineering, 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 ;, 1981), by R. Gamble, J. Strosnider, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering (page images at HathiTrust)
• Development of a mechanistic model for ECC penetration in a PWR downcomer : topical report / prepared by A. Segev, R.P. Collier. (The Commission, 1980), by Aryeh Segev, Robert P. Collier, Battelle Memorial Institute. Columbus Laboratories, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Application of Battelle's mechanistic model to lower plenum refill (The Commission, 1981), by Aryeh Segev, Robert P. Collier, Battelle Memorial Institute. Columbus Laboratories, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Study of safety relief valve operation under ATWS conditions (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, 1979), by E. S. Hutmacher, J. B. Brukiewa, B. J. Nesmith, Rockwell International, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Surface spectroscopy of pressure vessel steel fatigue fracture surface films formed in PWR environments (Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by H. E. Hanninen, W. H. Cullen, M. Vulli, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering, and Materials Engineering Associates (page images at HathiTrust)
• A summary of the operation of the ANL-2 pressurized water loop at the MTR / by C.C. Crothers. (Argonne National Laboratory, 1964), by C. C. Crothers, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Chemical decontamination of the ANL-2 high-pressure water loop (Argonne National Laboratory, 1960), by C. C. Crothers, U.S. Atomic Energy Comission, and Argonne National Laboratory (page images at HathiTrust)
• Study of 40 megawatt pressurized water, boiling water, and organic moderated reactors for production of process steam (Argonne National Laboratory, 1959), by L. E. Link, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Postirradiation evaluation of zircaloy-2 PRTR pressure tubes. Part I (Hanford Atomic Products Operation, 1962), by L. J. Defferding, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Reactor and Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part I, September, 1960--May, 1962 (Hanford Atomic Products Operation, 1962), by D. R. Doman, P. J. Pankaskie, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Reactor and Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Review of power and heat reactor designs : domestic and foreign (U.S. Atomic Energy Commission, 1963), by E. R. Appleby, 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. Finance and Administration Operation (page images at HathiTrust)
• Review of power and heat reactor designs : domestic and foreign (U.S. Atomic Energy Commission, 1961), by E. R. Appleby, U.S. Atomic Energy Commission, Hanford Works, and Hanford Atomic Products Operation. Hanford Laboratories Operation (page images at HathiTrust)
• SPERT II reactor facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by C. R. Montgomery, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Note on the effect on reactivity of water annuli in large void spaces in the Spert-I reactor core (U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by G. O. Bright, C. R. Toole, 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)
• The SPERT III reactor nuclear startup (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by R. A. Zahn, C. R. Toole, W. J. Neal, F. Schroeder, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Phase change indicators for subambient temperatures (National Aeronautics and Space Administration ;, 1970), by D. R. Kasanof, E. Kimmel, Langley Research Center, and Tempil Corporation (page images at HathiTrust)
• A survey of bulk-boiling studies in pressurized water reactor systems (Brookhaven National Laboratory, 1960), by H. Susskind, U.S. Atomic Energy Commission, Brookhaven National Laboratory, and Inc Associated Universities (page images at HathiTrust)
• Design calculations for steam system for 10 Mw pressurized-water power reactor (Technical Information Extension, 1955), by R. C. Robertson, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
• Development of methods for sealing ends of PWR fuel rods (U.S. Atomic Energy Commission, Technical Information Service Extension, 1957), by J. J. Vagi, D. C. Martin, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Nondestructive inspection of PWR reference fuel-element closures (U.S. Atomic Energy Commission, Technical Information Service Extension, 1957), by D. E. Stutz, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Radiographic procedures for PWR-type fuel elements (U.S. Atomic Energy Commission, Technical Information Service, 1955), by Samuel A. Wenk, Kenneth D. Cooley, Merle L. Rhoten, David E. Stutz, Battelle Memorial Institute, and U.S. Atomic Energy Commission. Technical Information Service (page images at HathiTrust)
• High-strength materials for pressurized-water in-pile tubes (Battelle Memorial Institute ;, 1957), by Fred H. Lyon, Raeman P. Sopher, Walter K. Boyd, Ward F. Simmons, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Studies of flow and mixing in a 0.4-scale model of the PWR Core 2 reactor (Battelle Memorial Institute, 1962), by Lawrence J. Flanigan, Herbert R. Hazard, Gale R. Whitacre, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A study of rotary shaft-sealing concepts for pressurized-water reactor application (Battelle Memorial Institute, 1964), by Daniel R. Grieser, U.S. Atomic Energy Commission, Battelle Memorial Institute, and Euratom (page images at HathiTrust)
• Model studies of flow in PWR Core 2 fuel assemblies (Battelle Memorial Institute, 1965), by Lawrence J. Flanigan, William D. Beck, Clarkson L. Coffin, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Tables of effective neutron cross sections in water moderated reactors (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1957), by H. Dean Brown, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Free-surface separation of steam and water for application in a marine reactor at 1000 PSIG (United States Atomic Energy Commission, Office of Technical Information ;, 1960), by A. G. Steamer, H. D. Ongman, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
• Shippingport operations : from start-up to first refueling, December 18, 1957 to October 7, 1959 ([publisher not identified], 1960), by William E. Wynne, William H. Hamilton, John E. Gray, Bettis Atomic Power Laboratory, and Duquesne Light Company (page images at HathiTrust)
• Pressurized water reactor plant. (For sale by the Superintendent of Documents, U.S. Govt. Print. Off, 1972), by inc United Engineers & Constructors and U.S. Atomic Energy Commission. Division of Reactor Development and Technology (page images at HathiTrust)
• A review of Yankee operating data. (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1961., 1961), by U.S. Atomic Energy Commission. New York Operations Office and Inc Nuclear Utility Services (page images at HathiTrust)
• The effects of changing economic conditions on fuel cycle costs in pressurized water reactors : a report to East Central Nuclear Group, Inc. (United States Atomic Energy Commission, Technical Information Service, 1963), by Manson Benedict, Max C. Richardson, Henri Fenech, U.S. Atomic Energy Commission, Massachusetts Institute of Technology. Department of Nuclear Engineering, and Inc East Central Nuclear Group (page images at HathiTrust)
• PM-1 parametric study report (United States Atomic Energy Commission, Technical Information Service ;, 1959), by J. S. Sieg, Martin Company. Nuclear Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The Shippingport pressurized water reactor : a bibliography of report literature (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, 1958., 1958), by Sidney F. Lanier and U.S. Atomic Energy Commission. Technical Information Service (page images at HathiTrust)
• Pressurized water reactors : a literature search (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, [1959], 1959), by Sidney F. Lanier and U.S. Atomic Energy Commission (page images at HathiTrust)
• The Pressurized Water Reactor Forum, held December 2, 1955, at Mellon Institute, Pittsburgh. (Washington, D.C. : Industrial Information Branch, Technical Information Service, Atomic Energy Commission, 1956., 1956), by U.S. Atomic Energy Commission. Technical Information Service (page images at HathiTrust)
• Small-sized nuclear power plant program (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1959., 1959), by U.S. Atomic Energy Commission (page images at HathiTrust)
• Small size pressurized water reactor specifications (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1960., 1960), by U.S. Atomic Energy Commission and Gibbs & Hill (page images at HathiTrust)
• Advanced pressurized water reactor study : appendixes to phase 1 report (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1959., 1959), by U.S. Atomic Energy Commission. Division of Reactor Development, U.S. Atomic Energy Commission, inc Combustion Engineering, and Stone and Webster Engineering Corporation (page images at HathiTrust)
• Pressure vessel and piping codes applicable to the PWR reactor plant (Washington, D.C. : Office of Technical Services, Department of Commerce, 1957., 1957), by J. F. Dobinsky, T. R. Moffette, M. B. Andrew, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The Shippingport Pressurized Water Reactor Project catalog of document abstracts. (Washington, D.C. : Office of Technical Services, Department of Commerce, 1961., 1961), by Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The Shippingport Pressurized Water Reactor Project catalog of document abstracts. (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Test rig for use in wear and friction studies in a water environment (Pittsburgh, Pennsylvania. : Bettis Atomic Power Laboratory, 1965., 1965), by N. B. Dewees, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Development and properties of silver-base alloys as control rod materials for pressurized water reactors (Pittsburgh, Pennsylvania : Bettis Atomic Power Laboratory, 1959., 1959), by I. Cohen, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The calculation of pressure drop and flow distribution within a reactor vessel in a pressurized water nuclear reactor system (Pittsburgh, Pennsylvania : Bettis Atomic Power Laboratory, 1959., 1959), by J. S. Busch, C. F. Bonilla, L. L. Lynn, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Summary of calculational and experimental physics results for Shippingport PWR-1 seed 1 (Pittsburgh, Pennsylvania : Bettis Atomic Power Laboratory, 1961., 1961), by R. P. Christman, D. H. Jones, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• CVR pressurizer simulator study (Washington, D.C. : Office of Technical Services, Department of Commerce, 1953., 1953), by W. M. Gajewski, J. N. Grace, Bettis Atomic Power Laboratory, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation. Atomic Power Department (page images at HathiTrust)
• Calculation of fission product activity in pressurized water reactor from a seed plate failure (Washington, D.C. : Office of Technical Services, Department of Commerce, 1957., 1957), by P. W. Frank, U.S. Atomic Energy Commission, Westinghouse Electric Corporation, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The performance of base-form ion exchangers for pH control and removal of radioisotopes from a pressurized water reactor system (Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by G. P. Simon, W. T. Lindsay, C. S. Abrams, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Stress analysis with applications to pressurized water reactors (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by P. L. Pfennigwerth, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The properties of hafnium from a PWR Core 1 control rod after one seed life exposure (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by G. J. Salvaggio, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Properties of a hafnium control rod after exposure during two seed lives in pwr core 1 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by G. J. Salvaggio, J.P. Bacca, F.A. Nichols, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Radiation damage exposure and embrittlement of reactor pressure vessels (Washington, D.C. : Office of Technical Services, Department of Commerce, 1964., 1964), by K. Shure, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• 1000-MWE central station power plants investment cost study ([Washington, D.C.] : [For sale by the Supt. of Docs., U.S. Govt. Print Off.], 1972., 1972), by inc United Engineers & Constructors and U.S. Atomic Energy Commission. Division of Reactor Development and Technology (page images at HathiTrust)
• Fort Calhoun Station : unit 2 : Omaha Public Power District (construction-permit stage) (Oak Ridge, Tennessee : Energy Research and Development Administration, Technical Information Center ; Springfield, Va. : For sale by the National Technical Information Service, 1976., 1976), by Wanda H. Williams, 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)
• Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports : resolution of generic technical activity A-12 (Washington, D.C. : Division of Operating Reactors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1979., 1979), by J. J. Zudans, H. A. Levin, J. M. Hodge, R. P. Snaider, and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
• Standard technical specifications for Combustion Engineering pressurized water reactors (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Operating Reactors ;, 1979), by Martin Virgilio and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
• Convective heat transfer within spent fuel canisters : an experimental laboratory study (Battelle Office of Nuclear Waste Isolation, 1981), by M. Keyhani, R. N. Christensen, F. A. Kulacki, United States. Department of Energy, and Battelle Memorial Institute. Office of Nuclear Waste Isolation (page images at HathiTrust)
• The strain aging and heat treatment properties of N-reactor connector tubes (Hanford Atomic Products Operation, 1963), by H. J. Pessl, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Prototype burst test unit for irradiated pressure tubes (Hanford Atomic Products Operation, 1963), by P. M. Jackson, P. J. Pankaskie, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Consolidated nuclear steam generator for merchant ship application : a conceptual design. (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by Babcock & Wilcox Company and U.S. Atomic Energy Commission (page images at HathiTrust)
• Specifications for swage compacted, mixed oxide (UO₂-PuO₂), fuel elements for the PRTR (MARK I-M) (Hanford Atomic Products Operation, 1963), by Hanford Atomic Products Operation. Ceramics Research and Development Operation and U.S. Atomic Energy Commission (page images at HathiTrust)
• The design study of fluid engine power systems (Oak Ridge, Tennessee : United States Atomic Energy Commission, Division of Technical Information, 1963., 1963), by C. H. Baker, A. V. Pradhan, R. S. Pauliukonis, T. A. Hunter, Cleveland Pneumatic Tool Company, and U.S. Atomic Energy Commission. New York Operations Office (page images at HathiTrust)
• Specifications for vibrationally compacted, mixed oxide (UO₂-PuO₂) fuel elements for the PRTR (MARK I-L) (Hanford Atomic Products Operation, 1963), by Hanford Atomic Products Operation. Ceramics Research and Development Operation and U.S. Atomic Energy Commission (page images at HathiTrust)
• Economic evaluation of a 300 Mwe fast supercritical pressure power reactor (Hanford Atomic Products Operation, 1963), by D. T. Aase, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Economic evaluation of a 300-Mw(e) supercritical pressure power reactor (Hanford Atomic Products Operation, 1961), by R. K. Marshall, R. D. Leggett, R. D. Widrig, K. G. Toyoda, J. J. Regimbal, H. Harty, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Investigation of types of seals for main coolant pumps for large pressurized water reactor nuclear plants. (Technical Information Service Extension ;, 1960), by U.S. Atomic Energy Commission and Ebasco Services Incorporated (page images at HathiTrust)
• In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part II, May and June, 1962 (Hanford Atomic Products Operation, 1962), by D. R. Doman, P. J. Pankaskie, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Carolinas Virginia tube reactor ; large plant study (Pittsburgh, 1963), by Westinghouse Electric Corporation. Atomic Power Division and R. G. McGrath (page images at HathiTrust)
• In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part III, July 1963 - November 1963 (Hanford Atomic Products Operation, 1963), by P. J. Pankaskie, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Effect of ²³⁶uranium and ²³⁷neptunium on the value of uranium used as feed for thermal power reactors ([Cambridge, Massachusetts] : Massachusetts Institute of Technology, Department of Nuclear Engineering, 1968., 1968), by Manson Benedict, Edward A. Mason, Terence Cashin Golden, David John Bauhs, U.S. Atomic Energy Commission, and Massachusetts Institute of Technology. Department of Nuclear Engineering (page images at HathiTrust)
• Shippingport operations during PWR core 1 depletion : December 1957 to February 1964 (Pittsburgh, Pennsylvania. : Bettis Atomic Power Laboratory, 1968., 1968), by R. T. Dressler, R. D. O'Hara, L. H. Kemmet, U.S. Atomic Energy Commission, Bettis Atomic Power Laboratory, and Duquesne Light Company (page images at HathiTrust)
• Technology, safety and costs of decommissioning a reference pressurized water reactor power station (Washington, D.C. : Nuclear Regulatory Commission, Office of Standards Development, Division of Engineering Standards, 1978-, 1978), by R. I. Smith, W. E. Kennedy, G. J. Konzek, and U.S. Nuclear Regulatory Commission. Division of Engineering Standards (page images at HathiTrust)
• Effect of containment venting on the risk from LWR meltdown accidents ([Washington, D.C.] : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Probablistic Analysis Branch, 1978., 1978), by P. Cybulskis, R. S. Denning, R. O. Wooton, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Branch, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Steam-water mixing and system hydrodynamics program : task 4 (Washington, D.C. : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, 1978-, 1978), by Battelle Memorial Institute. Columbus Laboratories, J.S. Liu, L. J. Flanigan, R. C. Dykhuizen, R. P. Collier, Ronald A. Cudnik, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Steam generator tube integrity program : annual progress report. (Washington, D.C. : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research ; 1978-, 1978), by M. Vagins, R. A. Clark, C. J. Morris, R. L. England, J. M. Alzheimer, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Study of safety relief valve operation under ATWS conditions (Washington, D. C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1979., 1979), by E. S. Hutmacher, S. D. Whitten, Energy Technology Engineering Center (U.S.), and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Steam-water mixing and system hydrodynamics program - task 4 : quarterly progress 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, 1979., 1979), by Robert P. Collier, Aryeh Segev, Jim S. Liu, Robert E. Kurth, Lawrence J. Flanigan, Joseph A. Dworak, Thomas A. Bishop, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Steam-water mixing and system hydrodynamics program - task 4 : quarterly progress report January - March 1980 (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1980., 1980), by Aryeh Segev, R. P. Collier, J. S. K. Liu, L. J. Flanigan, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Evaluation of cracking in feedwater piping adjacent to the steam generators in nine pressurized water reactor plants (Washington, D. C. : 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, 1980., 1980), by Alfred Goldberg, Robert G. Scott, Ronald D. Streit, Lawrence Livermore National Laboratory, and U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (page images at HathiTrust)
• Steam-water mixing and system hydrodynamics program - task 4 : quartely report, July - September 1980 (Washington, D.C. U.S. Nuclear Regulatory Commission, 1980., 1981), by Aryeh Segev, Robert P. Collier, Battelle Memorial Institute. Columbus Laboratories, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Corrosion and wear handbook for water-cooled reactors. (McGraw-Hill, 1957), by D. J. DePaul (page images at HathiTrust; US access only)
• Fuel inventory and afterheat power studies of uranium-fueled pressurized water reactor fuel assemblies using the SAS2 and ORIGEN-S modules of scale with an ENDF/B-V updated cross section library (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, 1982., 1982), by J. C. Ryman, C. V. Parks, C. C. Webster, O. W. Hermann, Oak Ridge National Laboratory. Computer Sciences Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Investigation of shell cracking on the steam generators at Indian Point, unit no. 3 (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983), by C. Czajkowski, Brookhaven National Laboratory. Department of Nuclear Energy, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering (page images at HathiTrust)
• Fatigue crack growth rates of A 508-2 steel in pressurized, high temperature water (The Commission, 1983), by W. H. Cullen, Inc ENSA, Materials Engineering Associates, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Iodine behavior in steam generator tube rupture accidents (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1982., 1982), by S. Raghuram, H. Jordan, R. S. Denning, Paul Baybutt, Battelle Memorial Institute. Columbus Laboratories, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Pressurized water reactor - full-length emergency cooling heat transfer (PWR-FLECHT) test project (Washington, D. C. : Atomic Energy Division, Idaho Operations Office, U.S. Atomic Energy Commission, 1969., 1969), by S. G. Forbes, N. K. Sowards, T. R. Wilson, U.S. Atomic Energy Commission, and Phillips Petroleum Company (page images at HathiTrust)
• Reactivity accident test results and analyses for the SPERT III e-core -- a small, oxide-fueled, pressurized-water reactor (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1969., 1969), by R. K. McCardell, J. E. Houghtaling, D. I. Herborn, Phillips Petrolium Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel rod deformation in the SPERT III oxide e-core (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1969., 1969), by W. H. Etz, Phillips Petrolium Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Semiscale blowdown and emergency core cooling (ECC) project test report -- test 803 through 820 (Idaho Falls, Idaho : Idaho Nuclear Corporation, 1970., 1970), by Harry W. Heiselmann, J. F. Whitbeck, D. J. Olson, U.S. Atomic Energy Commission. Idaho Operations Office, Allied Chemical Corporation, and Aerojet-General Corporation (page images at HathiTrust)
• Comparison of predictions from the reactor primary system decompression code (RELAP3) with decompression data from the semiscale blowdown and emergency core cooling (ECC) project (Idaho Falls, Idaho : Idaho Nuclear Corporation, 1970., 1970), by C. E. Slater, U.S. Atomic Energy Commission. Idaho Operations Office, Allied Chemical Corporation, and Aerojet-General Corporation (page images at HathiTrust)

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