Neutron irradiation embrittlement of reactor pressure vessel steels is an important ageing issue for the long term operation of light water reactors. A new embrittlement correlation method was developed by CRIEPI and the Japanese electric utilities in 2007. This method is primarily based on the fundamental understandings on the embrittlement mechanisms: i.e. microstructural changes were modeled by the mathematical form of rate equations, and the predicted microstructural changes were further correlated with the mechanical property changes in transition temperature region. The coefficients of the rate equations were optimized using the Japanese surveillance data of RPV embrittlement. This method was adopted as the revision of the Japanese code, JEAC 4201–2007, in 2007. In this paper, after a brief explanation on the new correlation method, the predictions of the new method will be investigated through comparisons with the previous correlation, JEAC4201–2004, and the US surveillance data in order to identify the characteristics of the new method.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels
Naoki Soneda,
Naoki Soneda
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
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Akiyoshi Nomoto
Akiyoshi Nomoto
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
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Naoki Soneda
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
Akiyoshi Nomoto
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
Paper No:
ICONE17-75320, pp. 423-430; 8 pages
Published Online:
February 25, 2010
Citation
Soneda, N, & Nomoto, A. "Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 423-430. ASME. https://doi.org/10.1115/ICONE17-75320
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