Abstract
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.
| Original language | English |
|---|---|
| Pages (from-to) | 116-127 |
| Number of pages | 12 |
| Journal | Journal of Nuclear Materials |
| Volume | 362 |
| Issue number | 1 |
| DOIs | |
| State | Published - May 15 2007 |
Funding
This research is sponsored by the Laboratory Directed Research and Development Seed Money Program and the Radiation Safety Information Computational Center of Oak Ridge National Laboratory, and by the Materials Science and Engineering Division, Office of Basic Energy Sciences, of the US Department of Energy, under contract DE-AC05-00OR22725 with UT-Battelle, LLC.
Keywords
- P1200
- R0300
- S0800