TAILIEUCHUNG - Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels. | Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors Nuclear Engineering and Technology 49 (2017) 1109e1112 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: Technical Note Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors Ji-Hyun Yoon*, Bong-Sang Lee Korea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-Gil, Yuseong-Gu, Daejeon, 34057, Republic of Korea a r t i c l e i n f o a b s t r a c t Article history: The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prereq- Received 20 December 2016 uisite for the long-term operation of nuclear power plants beyond their original design life. The expi- Received in revised form ration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates 7 April 2017 and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's Accepted 17 April 2017 Available online 11 May 2017 transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels. The applicability of the TTS model to predict the embrittlement of Korean RPVs made of SA533B-1 plates and welds was investigated in this study. It was concluded that the TTS model of 10 CFR Keywords: Embrittlement Trend Curve matched the trends of the radiation embrittlement in the SA533B-1 plates and welds better than Pressurized Thermal Shock did that of Regulatory Guide (RG) Rev. 2. This is attributed to the fact that the prediction perfor- Reactor Pressure Vessel mance of 10 CFR was enhanced by considering the difference in radiation embrittlement sensi- SA533B-1 tivity among the .

• Kỹ Thuật - Công Nghệ
• Nuclear engineering and technology
• Comparison of applicability of current transition temperature shift models
• SA533B 1 reactor pressure vessel steel of Korean nuclear reactors
• Korean nuclear reactors
• Aged reactor pressure vessels
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
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• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
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