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Research Papers: Nuclear Power

Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

[+] Author and Article Information
Naoki Soneda, Akiyoshi Nomoto

 Central Research Institute of Electric Power Industry, Komae, Tokyo 201-8511, Japan

J. Eng. Gas Turbines Power 132(10), 102918 (Jul 09, 2010) (9 pages) doi:10.1115/1.4001056 History: Received August 11, 2009; Revised October 01, 2009; Published July 09, 2010; Online July 09, 2010

Neutron irradiation embrittlement of reactor pressure vessel steels is an important aging issue for the long-term operation of light water reactors. A new embrittlement correlation method was developed by Central Research Institute of Electric Power Industry 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, JEAC4201-2007, 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 U.S. surveillance data in order to identify the characteristics of the new method.

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Copyright © 2010 by American Society of Mechanical Engineers
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Figures

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Figure 1

Comparison of the measured transition temperature shifts in the Japanese surveillance program with the old and new Japanese embrittlement correlation

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Figure 2

Comparison of the predictions by JEAC4201-2004 and JEAC4201-2007 for the medium Cu base metal under PWR conditions

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Figure 3

Comparison of the predictions by JEAC4201-2004 and JEAC4201-2007 for the high copper base metal under BWR conditions

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Figure 4

Adjusted predictions by JEAC4201-2004 with high and low flux capsule data of BWR

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Figure 5

Adjusted predictions by JEAC4201-2004 with only low flux capsule data of BWR

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Figure 6

Adjusted predictions by JEAC4201-2007 with high and low flux capsule data of BWR. The trend curves are for the sixth capsule data.

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Figure 7

Comparison of the U.S. surveillance data and the JEAC4201-2004 predictions

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Figure 8

Comparison of the U.S. surveillance data and the JEAC4201-2007 predictions

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Figure 9

Prediction error of the (a) JEAC4201-2004 and (b) JEAC4201-2007 correlations as copper content for the U.S. surveillance data

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Figure 10

Prediction error of the (a) JEAC4201-2004 and (b) JEAC4201-2007 correlations with nickel content for the U.S. surveillance data

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Figure 11

Error of the JEAC4201-2007 predictions adjusted for the U.S. surveillance data

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