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Displaying 1-50 of 192 results
Quality control in fabrication of nuclear pressure vessels [by] Robert D. Wylie and Warren J. McGonnagle.
- Text
- New York, Rowman and Littlefield [c1964]
- 1964
- 1 Item
Item details Format Call Number Item Location Text JSE 73-1577 Offsite Not available - Please for assistance.Rules for construction of nuclear power plant components. Division 2: Code for concrete reactor vessels and containments. 1975 ed.
- Text
- New York, American Society of Mechanical Engineers, 1975.
- 1975
- 1 Item
Item details Format Call Number Item Location Text JSF 76-54 Offsite Not available - Please for assistance.Periodic inspection of pressurized components : a conference / arranged by the Pressure Vessels Section of the Applied Mechanics Group and the Nuclear Energy Group of the Institution of Mechanical Engineers, London, 4-6 June 1974.
- Text
- London ; New York : Mechanical Engineering Publications for the Institution of Mechanical Engineers, 1975.
- 1975
- 1 Item
Item details Format Call Number Item Location Text JSG 76-129 Offsite Not available - Please for assistance.Lumped-parameter analysis for shear failure in the end slab of cylindrical prestressed concrete pressure vessels, by R. Higashionna and W. C. Schnobrich.
- Text
- Urbana, University of Illinois, 1970.
- 1970
- 1 Item
Item details Format Call Number Item Location Text JSF 76-209 Offsite Not available - Please for assistance.The design and construction of prestressed concrete reactor vessels / [FIP Commission on Concrete Pressure and Storage Vessels].
- Text
- Slough [Eng.] : FIP, 1978.
- 1978
- 1 Item
Item details Format Call Number Item Location Text JSF 80-185 Offsite Not available - Please for assistance.Nuclear heat transport / M. M. El-Wakil.
- Text
- La Grange Park, Ill. : American Nuclear Society, c1978.
- 1978
- 1 Item
Item details Format Call Number Item Location Text JSE 80-866 Offsite Not available - Please for assistance.Trends in reactor pressure vessel and circuit development / edited by R.W. Nichols.
- Text
- London : Applied Science Publishers, c1980.
- 1980
- 1 Item
Item details Format Call Number Item Location Text JSE 81-1154 Offsite Not available - Please for assistance.Stress indices and stress intensification factors of pressure vessel and piping components : presented at the joint conference of the Pressure Vessels and Piping, Materials, Nuclear Engineering, Solar Energy Divisions, Denver, Colorado, June 21-25, 1981 / sponsored by the Pressure Vessels and Piping Division, ASME ; edited by R.W. Schneider, E.C. Rodabaugh.
- Text
- New York, N.Y. (345 E. 47th St., New York 10017) : American Society of Mechanical Engineers, c1981.
- 1981
- 1 Item
Item details Format Call Number Item Location Text JSF 82-320 Offsite Not available - Please for assistance.Plate inspection programme, PISC : report / from the Plate Inspection Steering Committee (PISC) on the ultrasonic examination of three test plates using the "PISC" procedure based upon the ASME XI code.
- Text
- Paris (France): Nuclear Energy Agency, Committee on the Safety of Nuclear Installations, Organisation for Economic Co-operation and Development, 1979.
- 1979
- 1 Item
Item details Format Call Number Item Location Text JSF 82-407 Offsite Not available - Please for assistance.Ultrasonic inspection of heavy section steel components : the PISC II final report / edited by R.W. Nichols and S. Crutzen.
- Text
- London ; New York : Elsevier Applied Science, c1988.
- 1988
- 1 Item
Item details Format Call Number Item Location Text JSD 89-312 Offsite Not available - Please for assistance.Radiation embrittlement of nuclear reactor pressure vessel steels : an international review (fourth volume) / Lendell E. Steele, editor.
- Text
- Philadelphia, PA : ASTM, c1993.
- 1993
- 1 Item
Item details Format Call Number Item Location Text JSF 93-464 Offsite Not available - Please for assistance.Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension / William R. Corwin, Fahmy M. Haggag, and William L. Server, editors.
- Text
- Philadelphia, PA : ASTM, c1993.
- 1993
- 1 Item
Item details Format Call Number Item Location Text JSE 94-411 Offsite Not available - Please for assistance.Three Mile Island reactor pressure vessel investigation project : achievements and significant results : proceedings of an open forum sponsored by the OECD Nuclear Energy Agency and the United States Nuclear Regulatory Commission, Boston (USA), 20-22 October 1993.
- Text
- Paris : 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 JSE 94-2102 Offsite Not available - Please for assistance.Effects of radiation on materials : 17th international symposium / David S. Gelles ... [et al.], editors.
- Text
- West Conshohocken, PA : ASTM, c1996.
- 1996
- 1 Item
Item details Format Call Number Item Location Text JSE 96-1244 Offsite Not available - Please for assistance.Contenitore metallico per impianti nucleari.
- Text
- Roma, 1964.
- 1964
- 1 Item
Item details Format Call Number Item Location Text PAWF (Cesari, F. Contenitore metallico per impianti nucleari) 1964 Offsite Not available - Please for assistance.Analysis of reactor vessel radiation effects surveillance programs. Prepared by L. E. Steele and C. Z. Serpan, Jr.
- Text
- Philadelphia, American Society for Testing and Materials [1970]
- 1970
- 2 Items
Item details Format Call Number Item Location Text VEE (American Society for Testing Materials. Special technical publication. no. 481) Offsite Not available - Please for assistance.Item details Format Call Number Item Location Text VEE (American Society for Testing Materials. Special technical publication. no. 481) no. 481 Offsite Not available - Please for assistance.Compilation of contract research for the Materials Engineering Branch, Division of Engineering Technology.
- Text
- Washington, D.C. : Materials Engineering Branch, Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : NRC/GPO Sales Program, U.S. Nuclear Regulatory Commission, [distributor
- unknown-present
LWR pressure vessel surveillance dosimetry improvement program / Hanford Engineering Development Laboratory ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
- Text
- Washington, DC : The Division : NRC/GPO Sales Program, U.S. Nuclear Regulatory Commission, [distributor
- unknown-present
Heavy-section steel technology program / prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.
- Text
- Washington, D.C. : The Office : Available from Supt. of Docs., U.S. G.P.O. ; Springfield, Va. : National Technical Information Service, [distributor
- unknown-present
Heavy-section steel technology program [microform] / prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research ; prepared by the Oak Ridge National Laboratory, Engineering Technology Division.
- Text
- Washington, D.C. : The Office : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service
- unknown-present
Compilation of contract research for the Materials Branch, Division of Engineering Safety [microform].
- Text
- Washington, D.C. : Materials Branch, Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : NRC/GPO Sales Program, U.S. Nuclear Regulatory Commission, [distributor], -1987.
- 198-1986
Compilation of contract research for the Materials Engineering Branch, Division of Engineering [microform].
- Text
- Washington, D.C. : Materials Engineering Branch, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- 1987-present
Heavy-section steel irradiation program [microform] / prepared by Oak Ridge National Laboratory ; prepared for the Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
- Text
- Washington, DC : The Division : Supt. of Docs., U.S. G.P.O. [distributor], 1990-
- 1990-present
Heavy-section steel irradiation program [microform] / prepared by Oak Ridge National Laboratory ; prepared for the Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
- Text
- Washington, DC : The Division : Supt. of Docs., U.S. G.P.O. [distributor], 1990-
- 1990-present
An overview of the low-upper-shelf toughness safety margin issue / prepared by J.G. Merkle.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1990.
- 1990
Analysis of the VENUS-3 experiments / prepared by R.E. Maerker.
- Text
- Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Extension and extrapolation of J-R curves and their application to the low upper shelf toughness issue / prepared by J.A. Joyce, E.M. Hackett.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991.
- 1991
Post-irradiation fracture toughness characterization of four lab-melt plates / prepared by A.L. Hiser.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Detection and characterization of indications in segments of reactor pressure vessels / prepared by K.V. Cook, R.A. Cunningham, Jr., R.W. McClung.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commisson, 1989.
- 1989
A finite element analysis of a reactor pressure vessel during a severe accident / prepared by R.S. Chambers.
- Text
- Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Neutron exposure parameters for the metallurgical test specimens in the sixth heavy-section steel irradiation series / prepared by L.F. Miller ... [et al.].
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 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
Core-concrete interactions using molten steel with zirconium on a basaltic basemat : the SURC-4 experiment / prepared by E.R. Copus ... [et al.].
- Text
- Washington, D.C. : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Universal treatment of plumes and stresses for pressurized thermal shock evaluations [microform] / prepared by T.G. Theofanous, S. Angelini, H. Yan.
- 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], 1992.
- 1992
Experimental and analytical investigation of the shallow-flaw effect in reactor pressure vessels [microform] / prepared by T.J. Theiss, D.K. Shum, S.T. Rolfe.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992.
- 1992
Post-irradiation fracture toughness characterization of four lab-melt plates / prepared by A.L. Hiser.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Preliminary structural evaluation of Trojan RCL subject to postulated RPV support failure / prepared by S.C. Lu.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
- 1990
Influence of fluence rate on radiation-induced mechanical property changes in reactor pressure vessel steels : final report on exploratory experiments / prepared by J.R. Hawthorne, A.L. Hiser.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
- 1990
PR-EDB, power reactor embrittlement data base, version 1 : program description / prepared by F.W. Stallmann, F.B.K. Kam, B.J. Taylor.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990-
- 1990-present
Regulatory analysis for the resolution of generic issue C-8, "main steam isolation valve leakage and LCS failure" / C.C. Graves.
- Text
- Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
- 1990
Mission survey for the Pressure Vessel Research User's Facility (PVRUF) / prepared by W.E. Pennell, C.E. Pugh.
- Text
- Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Warm prestress modeling : comparison of models and experimental results / prepared by R.B. Stonesifer, E.F. Rybicki, D.E. McCabe.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Development of equipment parameter tolerances for the ultrasonic inspection of steel components [microform] / prepared by E.R. Green ... [et al.].
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992-
- 1992-present
Round-Robin analysis of the behavior of a 1:6-scale reinforced concrete containment model pressurized to failure [microform] : posttest evaluations / prepared by D.B. Clauss.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
- 1989
Crack propagation in high strain regions of Sequoyah containment [microform] / prepared by L. Greimann, F. Fanous, D. Bluhm.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
- 1993
Analysis of thermal mixing and boron dilution in a PWR [microform] / prepared by J.G. Sun, W.T. Sha.
- Text
- Washington, DC : Division of Safety Programs, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
- 1993
Generic analyses for evaluation of low Charpy upper-shelf energy effects on safety margins against fracture of reactor pressure vessels [microform] / prepared by T.L. Dickson.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
- 1993
Initial results of the influence of biaxial loading on fracture toughness [microform] / prepared by T.J. Theiss ... [et al.].
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
- 1993
CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (Project FALSIRE) [microform] / prepared by B.R. Bass ... [et al.].
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1993.
- 1993
Statistically based reevaluation of PISC-II round robin test data [microform] / prepared by P.G. Heasler, T.T. Taylor, S.R. Doctor.
- Text
- Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1993.
- 1993
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