-
1
-
-
0345676056
-
State-of-the-art review on irradiation embrittlement surveillance and mitigation methods
-
Pelli R, Törröneon K (VTT). State-of-the-art review on irradiation embrittlement surveillance and mitigation methods. AMES Report.
-
AMES Report
-
-
Pelli, R.1
Törröneon, K.2
-
2
-
-
0345244364
-
Comparison of prediction formula for irradiation embrittlement of LWR vessel materials
-
Petrequin P (CEA). Comparison of prediction formula for irradiation embrittlement of LWR vessel materials. AMES Report.
-
AMES Report
-
-
Petrequin, P.1
-
3
-
-
0344813244
-
-
Radiation embrittlement of reactor vessel materials. May
-
US NRC Regulatory Guide 1.99, Revision 2, Radiation embrittlement of reactor vessel materials. May 1988.
-
(1988)
US NRC Regulatory Guide 1.99, Revision 2
-
-
-
4
-
-
0344381610
-
-
Code of Federal Regulation, Title 10, Part 50, article 61, Fracture toughness requirements for protection against pressurized thermal shock events. July 1991
-
Code of Federal Regulation, Title 10, Part 50, article 61, Fracture toughness requirements for protection against pressurized thermal shock events. July 1991.
-
-
-
-
5
-
-
0345676048
-
-
Code of Federal Regulation, Title 10, Part 50, Appendix G, Fracture toughness requirements. July 1991
-
Code of Federal Regulation, Title 10, Part 50, Appendix G, Fracture toughness requirements. July 1991.
-
-
-
-
6
-
-
0345244362
-
-
Code of Federal Regulation, Title 10, Part 50, Appendix H, Reactor vessel material surveillance program requirements. July 1991
-
Code of Federal Regulation, Title 10, Part 50, Appendix H, Reactor vessel material surveillance program requirements. July 1991.
-
-
-
-
7
-
-
0344381611
-
-
ASME Boiler and Pressure Vessel Code, Section III, Appendix G, Protection against non-ductile failure. 1992 edition + 1993 addenda. (Also included as Appendix G in Section XI of the ASME Code.)
-
ASME Boiler and Pressure Vessel Code, Section III, Appendix G, Protection against non-ductile failure. 1992 edition + 1993 addenda. (Also included as Appendix G in Section XI of the ASME Code.).
-
-
-
-
8
-
-
0345676049
-
-
ASME Code, Section XI, Appendix A, Analysis of flaws. 1992 edition + 1993 addenda
-
ASME Code, Section XI, Appendix A, Analysis of flaws. 1992 edition + 1993 addenda.
-
-
-
-
9
-
-
0345676047
-
-
ASME Code, Section XI, Appendix E, Evaluation of unanticipated operating events
-
ASME Code, Section XI, Appendix E, Evaluation of unanticipated operating events.
-
-
-
-
10
-
-
0345675988
-
-
Section 5.3.2, Pressure-temperature limits
-
US NRC Standard Review Plan, Section 5.3.2, Pressure-temperature limits. 1975.
-
(1975)
US NRC Standard Review Plan
-
-
-
12
-
-
0344813240
-
-
Evaluation of reactor pressure vessels with Charpy upper-shelf energy less than 50 ft-lb published for comment, September
-
US NRC Draft Regulatory Guide DG-1023, Evaluation of reactor pressure vessels with Charpy upper-shelf energy less than 50 ft-lb (published for comment, September 1993).
-
(1993)
US NRC Draft Regulatory Guide DG-1023
-
-
-
13
-
-
0344813242
-
-
ASME, Section XI, Appendix K, Assessment of reactor vessels with low upper shelf Charpy impact energy levels. Addenda, 1993
-
ASME, Section XI, Appendix K, Assessment of reactor vessels with low upper shelf Charpy impact energy levels. Addenda, 1993.
-
-
-
-
14
-
-
0345676033
-
-
Format and content of plant specific pressurized thermal shock safety analysis report for pressurized water reactors. January
-
US NRC Regulatory Guide 1.154, Format and content of plant specific pressurized thermal shock safety analysis report for pressurized water reactors. January 1989.
-
(1989)
US NRC Regulatory Guide 1.154
-
-
-
15
-
-
0345676043
-
-
Code of Federal Regulation, Title 10, Part 50, article 50-66, Requirement for thermal annealing of the reactor vessels. (Part 50, Proposed rule making, 31 October 1994.)
-
Code of Federal Regulation, Title 10, Part 50, article 50-66, Requirement for thermal annealing of the reactor vessels. (Part 50, Proposed rule making, 31 October 1994.).
-
-
-
-
17
-
-
84910348593
-
Order relative to the application of pressure vessel regulations to nuclear water boilers
-
27 February
-
Order relative to the application of pressure vessel regulations to nuclear water boilers. Journal Officiel de la République Française, 27 February 1974.
-
(1974)
Journal Officiel de la République Française
-
-
-
20
-
-
0344813238
-
-
EPRI-NP-6713, French verification of PWR vessel integrity. February 1990
-
EPRI-NP-6713, French verification of PWR vessel integrity. February 1990.
-
-
-
-
22
-
-
0344381602
-
-
Doc WG1-92/P6(EN), REP 2000 programme, Working Group Codes and Standards - SG vessel. May 1992
-
Doc WG1-92/P6(EN), REP 2000 programme, Working Group Codes and Standards - SG vessel. May 1992.
-
-
-
-
24
-
-
0344381591
-
-
KTA 3201-1, Section 3.2.4.2, Material specification
-
KTA 3201-1, Section 3.2.4.2, Material specification.
-
-
-
-
28
-
-
0344381588
-
-
Answers to AMES questionnaire by A M Kryukov (Kurchatov Institute) and Y Dragunov (EDO Gidropress), 5 September 1994
-
Answers to AMES questionnaire by A M Kryukov (Kurchatov Institute) and Y Dragunov (EDO Gidropress), 5 September 1994.
-
-
-
-
32
-
-
0345244347
-
A UK regulatory view of fracture mechanics
-
Miller AG. A UK regulatory view of fracture mechanics. Nuclear Engineering and Design 1991, 131:139-145.
-
(1991)
Nuclear Engineering and Design
, vol.131
, pp. 139-145
-
-
Miller, A.G.1
-
34
-
-
4243714133
-
Demonstration of integrity for the Sizewell 'B' PWR reactor vessel
-
ASME PVP, MPC, ASME
-
Reid R, Dowling AR, Rigg GJ, Airey GP. Demonstration of integrity for the Sizewell 'B' PWR reactor vessel. In: ASME PVP, Vol. 213, MPC, Vol. 32, Pressure vessel integrity. ASME, 1991.
-
(1991)
Pressure Vessel Integrity
, vol.32-213
-
-
Reid, R.1
Dowling, A.R.2
Rigg, G.J.3
Airey, G.P.4
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