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Volumn 75, Issue 14, 1998, Pages 979-1036

Survey of national regulatory requirements relevant to PWR pressure vessels

Author keywords

[No Author keywords available]

Indexed keywords

PRESSURE VESSEL;

EID: 0345189474     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0308-0161(97)00077-X     Document Type: Article
Times cited : (6)

References (35)
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    • State-of-the-art review on irradiation embrittlement surveillance and mitigation methods
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    • AMES Report
    • Pelli, R.1    Törröneon, K.2
  • 2
    • 0345244364 scopus 로고    scopus 로고
    • 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 scopus 로고
    • 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 scopus 로고    scopus 로고
    • 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 scopus 로고    scopus 로고
    • 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 scopus 로고    scopus 로고
    • 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 scopus 로고    scopus 로고
    • 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 scopus 로고    scopus 로고
    • 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 scopus 로고    scopus 로고
    • ASME Code, Section XI, Appendix E, Evaluation of unanticipated operating events
    • ASME Code, Section XI, Appendix E, Evaluation of unanticipated operating events.
  • 10
    • 0345675988 scopus 로고
    • 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 scopus 로고
    • 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 scopus 로고    scopus 로고
    • 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 scopus 로고
    • 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 scopus 로고    scopus 로고
    • 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
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    • 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 scopus 로고    scopus 로고
    • EPRI-NP-6713, French verification of PWR vessel integrity. February 1990
    • EPRI-NP-6713, French verification of PWR vessel integrity. February 1990.
  • 22
    • 0344381602 scopus 로고    scopus 로고
    • 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 scopus 로고    scopus 로고
    • KTA 3201-1, Section 3.2.4.2, Material specification
    • KTA 3201-1, Section 3.2.4.2, Material specification.
  • 28
    • 0344381588 scopus 로고    scopus 로고
    • 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 scopus 로고
    • 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 scopus 로고
    • 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


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.