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Title: The Development of Radiation Embrittlement Models for U. S. Power Reactor Pressure Vessel Steels

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.

Authors:
 [1];  [1];  [2]
  1. ORNL
  2. AOL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
Work for Others (WFO)
OSTI Identifier:
931480
DOE Contract Number:  
DE-AC05-00OR22725
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 362; Journal Issue: 1
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; EMBRITTLEMENT; IRRADIATION; NEUTRON FLUENCE; PLATES; POWER REACTORS; PRESSURE VESSELS; PWR TYPE REACTORS; RADIATIONS; REGULATORY GUIDES; STEELS; TRANSITION TEMPERATURE

Citation Formats

Wang, Jy-An John, Rao, Nageswara S, and Konduri, Savanthi. The Development of Radiation Embrittlement Models for U. S. Power Reactor Pressure Vessel Steels. United States: N. p., 2007. Web. doi:10.1016/j.jnucmat.2006.12.013.
Wang, Jy-An John, Rao, Nageswara S, & Konduri, Savanthi. The Development of Radiation Embrittlement Models for U. S. Power Reactor Pressure Vessel Steels. United States. doi:10.1016/j.jnucmat.2006.12.013.
Wang, Jy-An John, Rao, Nageswara S, and Konduri, Savanthi. Mon . "The Development of Radiation Embrittlement Models for U. S. Power Reactor Pressure Vessel Steels". United States. doi:10.1016/j.jnucmat.2006.12.013.
@article{osti_931480,
title = {The Development of Radiation Embrittlement Models for U. S. Power Reactor Pressure Vessel Steels},
author = {Wang, Jy-An John and Rao, Nageswara S and Konduri, Savanthi},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2006.12.013},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 362,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}