1 |
PVRC Ad Hoc Group on Toughness Requrements, 1972, 'PVRC Recommendations on Toughness Requirements for Ferritic Materials,' WRC BULLETIN 175
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2 |
USNRC, 1995, 'Fracture Toughness Requirements,' 10CFR50 App. G.
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3 |
ASME Boiler and Pressure Vessel Code Sec. XI, 1998, 'Fracture Toughness Criteria for Protection Against Failure,' Appendix G.
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4 |
Jang, C. H., 2000, 'The Effect of Reference Flaw Size on P-T Limit Curves for Pressurized Water Reactor,' Proceeding of PVP2000 Conference, July 23-27, Seattle, USA
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5 |
이택진, 최재붕, 김영진, 박윤원, 정명조, 2000, '원자로용기 건전성평가를 위한 RVIES 시스템의 개발,' 대한기계학회논문집 (A) 제 24 권, 제 8 호, pp. 2083-2090
과학기술학회마을
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6 |
ASME Boiler and Pressure Vessel Code Sec. II, 1995, 'Materials,' Part D
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7 |
장창희, 문호림, 정일석, 홍승열, 2001, '개선된 확률론적 파괴역학해석 전산코드개발 : VINTIN,' 한국원자력학회 2001 춘계학술발표회논문집, 2001. 5. 24-25, 제주
과학기술학회마을
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8 |
KAERI, 2000, 'The Final Report for the 5-th Surveillance Test of the Reactor Pressure Vessel Material (Capsule P) of Kori Nuclear Power Plant Unit 1,' KAERI-ST-K1-003/00
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9 |
Marshall, W., 1982, 'An assessment of the integrity of PWR pressure vessels,' Second Report by a Study Group under the chairmanship of Dr. W. Marshall, UKAEA
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10 |
ASME, 1997, ASME Boiler and Pressure Vessel Code Sec. XI, 'Alternative to Reference Flaw Orientation of Appendix G for Circumferential Welds in Reactor Vessel,' Code Case N-588
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11 |
ASME, 1999, ASME Boiler and Pressure Vessel Code Sec. XI, 'Alternative Reference Fracture Toughness for Development of P-T Limit Curves,' Code Case N-640
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12 |
USNRC, 1996, 'Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events,' 10 CFR 50 50.61
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13 |
USNRC, 1988, 'Radiation Embrittlement of Reactor Vessel Materials,' Regulatory Guide 1.99, Rev. 2
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14 |
EPRI, 1993, 'Reactor Coolant System Heatup/Cooldown Curve Calculator,' EPRI TR-102552
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15 |
ASME Boiler and Pressure Vessel Code Sec. III, 1989, 'Protection Against Nonductile Failure,' Appendix G.
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