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.
Skip Nav Destination
Article navigation
October 2010
Research Papers
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 201-8511, Japan
Search for other works by this author on:
Akiyoshi Nomoto
Akiyoshi Nomoto
Central Research Institute of Electric Power Industry
, Komae, Tokyo 201-8511, Japan
Search for other works by this author on:
Naoki Soneda
Central Research Institute of Electric Power Industry
, Komae, Tokyo 201-8511, Japan
Akiyoshi Nomoto
Central Research Institute of Electric Power Industry
, Komae, Tokyo 201-8511, JapanJ. Eng. Gas Turbines Power. Oct 2010, 132(10): 102918 (9 pages)
Published Online: July 9, 2010
Article history
Received:
August 11, 2009
Revised:
October 1, 2009
Online:
July 9, 2010
Published:
July 9, 2010
Citation
Soneda, N., and Nomoto, A. (July 9, 2010). "Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels." ASME. J. Eng. Gas Turbines Power. October 2010; 132(10): 102918. https://doi.org/10.1115/1.4001056
Download citation file:
Get Email Alerts
Cited By
Experimental Identification Of Blade Tip Rub Forces At Engine Relevant Temperatures And Speeds
J. Eng. Gas Turbines Power
Study Of Tandem Rotor Dual Wake Interaction With Downstream Stator Under Unsteady Numerical Approach
J. Eng. Gas Turbines Power
Experimental Design Validation of a Swirl-Stabilized Burner With Fluidically Variable Swirl Number
J. Eng. Gas Turbines Power (April 2025)
Experimental Characterization of a Bladeless Air Compressor
J. Eng. Gas Turbines Power (April 2025)
Related Articles
Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan
J. Eng. Gas Turbines Power (October,2010)
Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels
J. Eng. Mater. Technol (January,2000)
Yankee Reactor Pressure Vessel Surveillance: Notch Ductility Performance of Vessel Steel and Maximum Service Fluence Determined From Exposure During Cores II, III, and IV
J. Basic Eng (December,1967)
Radiation and Temper Embrittlement Processes in Advanced Reactor Weld Metals
J. Eng. Ind (August,1972)
Related Proceedings Papers
Related Chapters
Hydrogen Uptake and Embrittlement Susceptibility of Ferrite-Pearlite Pipeline Steels
International Hydrogen Conference (IHC 2016): Materials Performance in Hydrogen Environments
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
NRC Safety Research Priorities for Reactor Vessel Embrittlement, Annealing, and Surveillance Dosimetry
Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study