Research Catalog
New! Try our Article Search to discover online journals, books, and more from home with your library card.
Displaying 1-50 of 397 results
Thermal analysis of pressurized water reactors [by] L. S. Tong [and] Joel Weisman. Prepared under direction of the American Nuclear Society for the Division of Technical Information United States Atomic Energy Commission.
- Text
- Hinsdale, Ill., American Nuclear Society [c1970]
- 1970
- 1 Item
Item details Format Call Number Item Location Text JSE 72-91 Offsite High void tests at the Garigliano Nuclear Power Station, by F. Santasilia.
- Text
- [Bruxelles, Euratom] 1968.
- 1968
- 1 Item
Item details Format Call Number Item Location Text JSF 73-1337 Offsite Water cooled reactor safety: an assessment prepared for the Committee on Reactor Safety Technology.
- Text
- Paris, European Nuclear Energy Agency. Organisation for Economic Co-operation and Development; London, H.M.S.O., 1970.
- 1970
- 1 Item
Item details Format Call Number Item Location Text JSF 74-306 Offsite Réacteurs nucléaires à eau pressurisée, théorie, technologie et applications à la propulsion navale, par J. de Ladonchamps ... et J. J. Verdeau ...
- Text
- Paris, Masson et Cie, 1972.
- 1972
- 1 Item
Item details Format Call Number Item Location Text JSE 74-174 Offsite Light water : how the nuclear dream dissolved / Irvin C. Bupp & Jean-Claude Derian.
- Text
- New York : Basic Books, c1978.
- 1978
- 1 Item
Item details Format Call Number Item Location Text JSD 78-493 Offsite Phénomènes thermiques et hydrauliques non stationnaires : cycle de conférences tenu à Jouy-en-Josas du 10 au 15 octobre 1976 / C.E.A.-E.D.F., École d'été de mécanique des fluides.
- Text
- Paris : Eyrolles, 1978.
- 1978
- 1 Item
Item details Format Call Number Item Location Text JSE 80-79 Offsite Proceedings of American Nuclear Society Topical Meeting on Light Water Reactor Fuel Performance, Portland, Oregon, April 29-May 3, 1979 / presented by American Nuclear Society Oregon Section ; sponsored by the following American Nuclear Society divisions, Nuclear Fuel Cycle Division, Materials Science and Technology Division, Power Division.
- Text
- LaGrange Park, Ill. : The Society, c1979.
- 1979
- 1 Item
Item details Format Call Number Item Location Text JSF 81-129 Offsite Pressurised water reactor in the United Kingdom, 11 May 1982, Institution headquarters, Westminster, London / sponsored by the Power Industries Division of the Institution of Mechanical Engineers.
- Text
- London : published by Mechanical Engineering Publications for the Institution of Mechanical Engineers, 1982.
- 1982
- 1 Item
Item details Format Call Number Item Location Text JSG 84-83 Offsite Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators : held at Fuji Institute of Education and Training, Japan, May 28-June 2, 1978 / co-editors and co-chairmen, Hideya Okada, Roger Staehle ; sponsors, Electric Power Research Institute ... [et al.]
- Text
- Houston, Texas : National Association of Corrosion Engineers, c1982.
- 1982
- 1 Item
Item details Format Call Number Item Location Text JSF 86-1015 Offsite Proceedings / International Meeting on Light Water Reactor Severe Accident Evaluation, August 28 to September 1, 1983, Cambridge, Massachusetts ; John R. Coombe, general chairman.
- Text
- [Boston, Mass.] : Stone & Webster Engineering Corp., 1983.
- 1983
- 2 Items
Item details Format Call Number Item Location Text JSF 85-642 v. 1 Offsite Item details Format Call Number Item Location Text JSF 85-642 v. 2 Offsite Water coolant technology of power reactors / Paul Cohen.
- Text
- [La Grange Park, Ill.] : American Nuclear Society, c1980.
- 1980
- 1 Item
Item details Format Call Number Item Location Text JSE 86-1006 Offsite Water chemistry of nuclear reactor systems 3 : proceedings of an international conference organised by the British Nuclear Energy Society and co-sponsored by the Institution of Chemical Engineers and the Royal Society of Chemistry, Bournemouth, 17-21 October 1983.
- Text
- London : British Nuclear Energy Society, 1983.
- 1983
- 1 Item
Item details Format Call Number Item Location Text JSG 86-98 Offsite Proceedings of the International Atomic Energy Agency specialists' meeting on subcritical crack growth : held at Freiburg, Federal Republic of Germany, May 13-15, 1981 / edited by W.H. Cullen ; sponsored by International Atomic Energy Agency, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research ; proceedings prepared by Materials Engineering Associates, Inc. under subcontract to ENSA, Inc.
- Text
- 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, 1983.
- 1983
- 1 Item
Item details Format Call Number Item Location Text JSF 86-324 Offsite Guidebook to light water reactor safety analysis / edited by P.B. Abramson.
- Text
- Washington : Hemisphere Pub. Corp. ; Berlin ; New York : Distribution outside North America, Springer-Verlag, c1985.
- 1985
- 1 Item
Item details Format Call Number Item Location Text JSE 87-2180 Offsite Critical flow modelling in nuclear safety : a state-of-the-art report / by a Group of Experts of the NEA Committee on the Safety of Nuclear Installations, June 1982.
- Text
- Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, c1982.
- 1982
- 1 Item
Item details Format Call Number Item Location Text JBY Q-235 Offsite High converting water reactors / editor, Yigal Ronen.
- Text
- Boca Raton, Fla. : CRC Press, c1990.
- 1990
- 1 Item
Item details Format Call Number Item Location Text JSE 90-2151 Offsite International Conference on Electrical and Control Aspects of the Sizewell B PWR : 14-15 September, 1992 / organised by the Power Division of the Institution of Electrical Engineers, in association with the British Nuclear Energy Society ... [et al.] ; venue, Churchill College, Cambridge, UK.
- Text
- London : Institution of Electrical Engineers, c1992.
- 1992
- 1 Item
Item details Format Call Number Item Location Text JSG 94-7 Offsite The Economics of the nuclear fuel cycle.
- Text
- Paris : Nuclear Energy Agency, Organisation for Economic Co-operation and Development ; Washington, D.C. : OECD Publications and Information Centre [distributor], c1994.
- 1994
- 1 Item
Item details Format Call Number Item Location Text JBF 95-594 Offsite Safety features of operating light water reactors of western design / Mirela Gavrilas ... [et al.].
- Text
- Boca Raton : CRC Press, c1995.
- 1995
- 1 Item
Item details Format Call Number Item Location Text JSF 95-83 Offsite Water coolant technology of power reactors.
- Text
- New York, Gordon and Breach [1969]
- 1969
- 1 Item
Item details Format Call Number Item Location Text PAWF (Cohen, P. Water coolant technology of power reactors) 1969 Offsite The Shippingport pressurized water reactor, written by personnel of the Naval Reactors Branch, Division of Reactor Development, United States Atomic Energy Commission, Westinghouse Electric Corporation, Bettis Plant [and] Duquesne Light Company.
- Text
- Reading, Mass., Addison-Wesley Pub. Co. [1958]
- 1958
- 1 Item
Item details Format Call Number Item Location Text PAWF (Shippingport pressurized water reactor) Offsite Corrosion and wear handbook for water-cooled reactors.
- Text
- New York, McGraw-Hill, 1957.
- 1957
- 1 Item
Item details Format Call Number Item Location Text PAWF (DePaul, D. J. Corrosion and wear handbook for water-cooled reactors) 1957 Offsite Final safety evaluation report related to certification of the AP600 standard design docket no. 52-003. Supplement 1 [microform].
- Text
- Washington, DC : Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1999.
- 1999
Simulation of LOCA 6" and LOCA 2" transients in the RHR of a PWR under low power conditions using RELAP5/MOD3.2 [microform] / prepared by S. Martorell ... [et al.].
- Text
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 2000]
- 2000
Nowadays tools for graphical post-processing of TRAC-BF1 results [microform] / prepared by P. Corcuera, M. Garcés.
- Text
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : [Supt. of Docs., U.S. G.P.O., distributor, 2000]
- 2000
Annual report for ... / prepared by Department of Chemical and Nuclear Engineering, University of Maryland; prepared for Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
- Text
- Washington, D.C. : The Dept. ; [Springfield, VA : National Technical Information Service, distributor], 1987-
- unknown-present
Steam generator operating experience, update for ...
- Text
- Washington, D.C. : Division of Engineering and Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service [distributor
- unknown-present
Auxiliary feedwater system risk-based inspection guide for the J.M. Farley Nuclear Power Plant / prepared by T.V. Vo ... [et al.].
- Text
- Washington, DC : Division of Radiation Protection and Emergency Preparedness, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1990.
- 1990
Closeout of IE bulletin 79-21 : temperature effects on level measurements / prepared by R.S. Dean, W.J. Foley, A. Hennick.
- Text
- Washington, DC : Division of Emergency Preparedness and Engineering Response, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, 1986.
- 1986
MELPROG-PWR/MOD1, a two-dimensional, mechanistic code for analysis of reactor core melt progression and vessel attack under severe accident conditions / edited by S.S. Dosanjh ; contributors, J.L. Tomkins ... [et al.].
- Text
- Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
RELAP5/MOD2 assessment, OECD-LOFT small break experiment LP-SB-03 / prepared by S. Guntay.
- Text
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor] ; Springfield, VA : National Technical Information Service [distributor, 1990]
- 1990
BWR and PWR off-normal event descriptions.
- Text
- Washington, DC : Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.
- 1987
NRC integrated program for the resolution of unresolved safety issues A-3, A-4, and A-5 regarding steam generator tube integrity : final report.
- Text
- Washington, DC : Division of Engineering and System Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1988.
- 1988
Multiloop integral system test (MIST) : MIST facility functional specification / T.F. Habib ... [et al.] ; prepared by Babcock & Wilcox, Nuclear Power Division ; Babcock & Wilcox, Research and Development Division.
- Text
- Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991.
- 1991
Safety evaluation report related to the preliminary design of the standard nuclear steam supply reference system, RESAR SP/90 : docket no. STN 50-601, Westinghouse Electric Corporation, Incorporated.
- Text
- [Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation : Supt. of Docs., U.S. G.P.O. [distributor, 1991]
- 1991
Regulatory analysis for the resolution of Generic issue 130 : essential service water system failures at multi-unit sites / V. Leung, D. Basdekas, G. Mazetis.
- Text
- Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991.
- 1991
Accident management information needs / prepared by D.J. Hanson ... [et al.].
- Text
- Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1990-
- 1990-present
Safety aspects of the Yankee Rowe Nuclear Powerplant : oversight hearing before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, One Hundred Second Congress, first session ... hearing held in Washington, DC, August 1, 1991.
- Text
- Washington : U.S. G.P.O. : For sale by the U.S. G.P.O., Supt. of Docs., Congressional Sales Office, 1992.
- 1992
Survey of boric acid corrosion of carbon steel components in nuclear plants / prepared by C.J. Czajkowski.
- Text
- Washington, DC : Division of Engineering Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : For sale by the Supt. of Docs., U.S. G.P.O., 1990.
- 1990
Inclusion of unstable ductile tearing and extrapolated crack-arrest toughness data in PWR vessel integrity assessment / prepared by T.L. Dickson, R.D. Cheverton, and D.K. Shum.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
- 1990
Hydrogen combustion, control, and value-impact analysis for PWR dry containments / prepared by J.W. Yang, Z. Musicki, S. Nimnual.
- Text
- Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991.
- 1991
Analysis of the UPTF separate effects test 11 (steam-water countercurrent flow in the broken loop hot leg) using RELAP5/MOD [microform] / prepared by M.J. Dillistone.
- Text
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor] ; Springfield, VA : National Technical Information Service [distributor, 1992]
- 1992
Assessment of RELAP5/MOD2, cycle 36.04 against LOFT small break experiment L3-5 [microform] / prepared by J. Eriksson.
- Text
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor] ; Springfield, VA : National Technical Information Service [distributor, 1992]
- 1992
Time step and mesh size dependencies in the heat conduction solution of a semi-implicit, finite difference scheme for transient two-phase flow [microform] / prepared by R. O'Mahoney.
- Text
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor] ; Springfield, VA : National Technical Information Service [distributor, 1992]
- 1992
Assessment of ISLOCA risk-methodology and application to a Babcock and Wilcox nuclear power plant [microform] / prepared by W.J. Galyean, D. I. Gertman.
- Text
- Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
- 1992
Interfacing systems LOCA : pressurized water reactors / prepared by G. Bozoki, P. Kohut, R. Fitzpatrick.
- Text
- Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Numerical simulation of natural circulation phenomena in a PWR during TMLB' transients prior to core damage / prepared by Y.S. Cha ... [et al.].
- Text
- Washington, DC : Division of Reactor Accident Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Iodine speciation and partitioning in PWR steam generator accidents : final report / prepared by E.C. Beahm ... [et al.].
- Text
- Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Assessment of RELAP5/MOD2 cycle 36.04 with LOFT large break LOCE L2-3 [microform] / prepared by Y.S. Bang, H.J. Kim, S.H. Kim.
- Text
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor] ; Springfield, VA : National Technical Information Service [distributor, 1992]
- 1992
TRAC-PF1 code assessment using OECD LOFT LP-FP-1 experiment [microform] / prepared by F.J. Barbero.
- Text
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor] ; Springfield, VA : National Technical Information Service [distributor, 1992]
- 1992
No results found from Digital Research Books Beta
Digital books for research from multiple sources world wide- all free to read, download, and keep. No Library Card is Required. Read more about the project.
