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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 1,423 - 1,432 (10page)
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The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs)has been extensively studied. This paper introduces an integrity assessment of an RPVsubjected to a PTS transient based on the French codes. In the USA, the “screening criterion”for maximum allowable embrittlement of RPV material is developed based on theprobabilistic fracture mechanics. However, in the French RCC-M and RSE-M codes, whichare developed based on the deterministic fracture mechanics, there is no “screening criterion”.
In this paper, the methodology in the RCC-M and RSE-M codes, which are used forPTS analysis, are firstly discussed. The bases of the French codes are compared with ASMEand FAVOR codes. A case study is also presented. The results show that the method in theRCC-M code that accounts for the influence of cladding on the stress intensity factor (SIF)may be nonconservative. The SIF almost doubles if the weld residual stress is considered.
The approaches included in the codes differ in many aspects, which may result in significantdifferences in the assessment results. Therefore, homogenization of the codes inthe long time operation of nuclear power plants is needed.
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참고문헌 (25)
참고문헌 신청
G.A. Qian / 2015 / Investigation on constraint effect of a reactor pressure vessel subjected to pressurized thermal shocks / Jour. Pre. Ves. Tec 137:1~7
M.Y. Chen / 2015 / The deterministic structural integrity assessment of reactor pressure vessels under pressurized thermal shock loading / Nucl. Eng. Des 288:84~91
W.E. Pennell / 1997 / Structural integrity assessment of aging nuclear reactor pressure vessels / Nucl. Eng. Des 172:27~47
US Nuclear Regulatory Commission / 1987 / Format and Content of Plant-specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors
US Nuclear Regulatory Commission / 1984 / Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events / US Nuclear Regulatory Commission
M.Y. Chen / 2015 / The deterministic structural integrity assessment of reactor pressure vessels under pressurized thermal shock loading / Nucl. Eng. Des 288:84~91
W.E. Pennell / 1997 / Structural integrity assessment of aging nuclear reactor pressure vessels / Nucl. Eng. Des 172:27~47
US Nuclear Regulatory Commission / 1987 / Format and Content of Plant-specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors
US Nuclear Regulatory Commission / 1984 / Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events / US Nuclear Regulatory Commission
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