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Volumn 171, Issue 1-3, 1997, Pages 1-14

US Nuclear Regulatory Commission research for primary system integrity regulations

Author keywords

[No Author keywords available]

Indexed keywords

CODES (STANDARDS); ENGINEERING RESEARCH; LAWS AND LEGISLATION; NUCLEAR ENGINEERING;

EID: 0031548947     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(96)01313-1     Document Type: Article
Times cited : (7)

References (42)
  • 2
    • 0039577959 scopus 로고    scopus 로고
    • American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, ASME, New York
    • American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, ASME, New York.
  • 3
    • 0040763492 scopus 로고    scopus 로고
    • American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section V, Rules for Nondestructive Examination, ASME, NewYork
    • American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section V, Rules for Nondestructive Examination, ASME, NewYork.
  • 4
    • 0040763491 scopus 로고    scopus 로고
    • American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Rules for InService Inspection of Nuclear Power Plant Components, ASME, New York
    • American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Rules for InService Inspection of Nuclear Power Plant Components, ASME, New York.
  • 5
    • 0040169513 scopus 로고    scopus 로고
    • ANSI/ASME B31.1, Power Piping, ASME, New York
    • ANSI/ASME B31.1, Power Piping, ASME, New York.
  • 6
    • 0039577960 scopus 로고    scopus 로고
    • Master matrix for WR pressure vessel surveillance standards
    • Section 12, Vol. 12.02, ASTM, Philadelphia, PA
    • ASTM, E706, Master matrix for WR pressure vessel surveillance standards, Annual Book of ASTM standards, Section 12, Vol. 12.02, ASTM, Philadelphia, PA.
    • Annual Book of ASTM Standards
  • 7
    • 0003562246 scopus 로고
    • lc, a measure of fracture toughness
    • Vol. 03.01, ASTM, Philadelphia
    • lc, a measure of fracture toughness, Annual Book of ASTM Standards, Vol. 03.01, ASTM, Philadelphia, 1993a, pp. 738-752.
    • (1993) Annual Book of ASTM Standards , pp. 738-752
  • 8
    • 34248679114 scopus 로고
    • Standard test method for determining J-R curves
    • Vol. 03.01, ASTM, Philadelphia, PA
    • ASTM, E 1152-87, Standard test method for determining J-R curves, Annual Book of ASTM Standards, Vol. 03.01, ASTM, Philadelphia, PA, 1993b, pp. 853-863.
    • (1993) Annual Book of ASTM Standards , pp. 853-863
  • 9
    • 0038985312 scopus 로고
    • 1a, of ferritic steels
    • vol. 03.01, ASTM, Philadelphia, PA
    • 1a, of ferritic steels, Annual Book of ASTM Standards, vol. 03.01, ASTM, Philadelphia, PA, 1993c, pp. 885-900.
    • (1993) Annual Book of ASTM Standards , pp. 885-900
  • 13
    • 0040763490 scopus 로고    scopus 로고
    • Code of Federal Regulations, Title 10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities
    • Code of Federal Regulations, Title 10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities.
  • 23
    • 0345396699 scopus 로고
    • Corrosion fatigue of ASTM A302B steel in high temperature water, the simulated nuclear reactor environment
    • O. Devereaux et al., (eds.), National Association of Corrosion Engineers, Houston, TX
    • T. Kondo, Corrosion fatigue of ASTM A302B steel in high temperature water, the simulated nuclear reactor environment, in O. Devereaux et al., (eds.), Corrosion Fatigue: Chemistry, Mechanics, and Microstructure. National Association of Corrosion Engineers, Houston, TX, 1973, pp. 539-556.
    • (1973) Corrosion Fatigue: Chemistry, Mechanics, and Microstructure , pp. 539-556
    • Kondo, T.1
  • 29
    • 77957013864 scopus 로고
    • NDE reliability: A major element in the defense in depth concept for nuclear power plant safety
    • Glasgow, 11-14 June
    • J. Muscara, NDE reliability: a major element in the defense in depth concept for nuclear power plant safety, Proc. 10th Int. Conf. on NDE in the Nuclear and Pressure Vessel Industries, Glasgow, 11-14 June 1990.
    • (1990) Proc. 10th Int. Conf. on Nde in the Nuclear and Pressure Vessel Industries
    • Muscara, J.1
  • 31
    • 0003579103 scopus 로고
    • Ultrasonic Inspection of Heavy Section Steel Components
    • Elsevier, London
    • R. Nichols and S. Crutzen (eds.), Ultrasonic Inspection of Heavy Section Steel Components, the PISC-II Final Report, Elsevier, London, 1988.
    • (1988) PISC-II Final Report
    • Nichols, R.1    Crutzen, S.2
  • 34
    • 0026910140 scopus 로고
    • Heavy-section steel technology program: Fracture issues
    • W.E. Pennell, Heavy-section steel technology program: fracture issues, J. Pressure Vessel Technol. 114 (1992) 255-264.
    • (1992) J. Pressure Vessel Technol. , vol.114 , pp. 255-264
    • Pennell, W.E.1
  • 35
    • 0040169434 scopus 로고
    • Recommendations on toughness requirements for ferritic materials
    • PVRC, Recommendations on toughness requirements for ferritic materials, WRC Bull. 175 (1972).
    • (1972) WRC Bull. , vol.175
  • 36
    • 0040763485 scopus 로고
    • Impact of US NRC reactor vessel embrittlement research on regulation of nuclear power plants, reactor dosimetry
    • C.Z. Serpan, Jr., Impact of US NRC reactor vessel embrittlement research on regulation of nuclear power plants, reactor dosimetry, ASTM Spec. Tech. Publ. 1228 (1994).
    • (1994) ASTM Spec. Tech. Publ. , vol.1228
    • Serpan C.Z., Jr.1
  • 37
    • 0021516973 scopus 로고
    • BWR pipe crack and weld clad overlay studies
    • W.J. Shack et al., BWR pipe crack and weld clad overlay studies, Nucl. Eng. Des. 89 (1985) 295-303.
    • (1985) Nucl. Eng. Des. , vol.89 , pp. 295-303
    • Shack, W.J.1
  • 38
    • 0040169437 scopus 로고
    • Technical issues and US Nuclear Regulatory Commission's research related to the primary pressure boundary
    • Kussmaul (ed.), Div. F, Elsevier, Amsterdam
    • L.C. Shao, Technical issues and US Nuclear Regulatory Commission's research related to the primary pressure boundary, in Kussmaul (ed.), SMiRT-12, Vol. A, Div. F, Elsevier, Amsterdam, 1993. pp. 21-37.
    • (1993) SMiRT-12 , vol.A , pp. 21-37
    • Shao, L.C.1
  • 39
    • 0016644484 scopus 로고
    • Neutron irradiation embrittlement of reactor pressure vessel steels
    • L.E. Steele, Neutron irradiation embrittlement of reactor pressure vessel steels, IAEA Vienna Tech. Rep. Ser. 163 (1975).
    • (1975) IAEA Vienna Tech. Rep. Ser. , vol.163
    • Steele, L.E.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.