SYMPOSIA PAPER Published: 01 January 2008

Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels


A new approach of utilizing information fusion technique is developed to predict the radiation embrittlement of reactor pressure vessel steels. The Charpy transition temperature shift data contained in the Power Reactor Embrittlement Database is used in this study. Six parameters—Cu, Ni, P, neutron fluence, irradiation time, and irradiation temperature—are used in the embrittlement prediction models. The results indicate that this new embrittlement predictor achieved reductions of about 49.5 % and 52 % in the uncertainties for plate and weld data, respectively, for pressurized water reactor and boiling water reactor data, compared with the Nuclear Regulatory Commission Regulatory Guide 1.99, Rev. 2. The implications of dose-rate effect and irradiation temperature effects for the development of radiation embrittlement models are also discussed.

Author Information

Wang, J., A.
Oak Ridge National Laboratory, Oak Ridge, TN
Rao, N., S. V.
Oak Ridge National Laboratory, Oak Ridge, TN
Konduri, S.
Oak Ridge National Laboratory, Oak Ridge, TN
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Developed by Committee: E10
Pages: 95–118
DOI: 10.1520/STP46567S
ISBN-EB: 978-0-8031-6826-8
ISBN-13: 978-0-8031-3421-8