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Title: Fracture Toughness Characterization of Highly irradiated Reactor Pressure Weld from the ATR-2 Experiment

Abstract

The UCSB ATR-2 irradiation experiment is designed to generate a new database on a wide variety of irradiated reactor pressure vessel (RPV) steels to fill a critical gap in predicting high fluence embrittlement for extended plant operation up to 80 years. A major focus in this experiment is to characterize the effects of irradiation temperature, neutron flux and fluence, and alloy chemistry on MNSP evolution, and model how these features impact hardening and embrittlement, manifested as shifts in ductile-to-brittle transition temperature. As part of these efforts, disk compact tension (DCT) specimens of three representative materials were included in the ATR-2 experiment to have direct measurement of transition fracture toughness shift and, thus, to have some benchmark data to compare outcoming predictive models with actual fracture toughness shifts. In addition, the attempts would be made to use these fracture toughness data to address the potential effect of high dose irradiation on the shape of the Master Curve for highly embrittled RPV material.This report provides data for the fracture toughness characterization of highly embrittled weld from Palisades steam generator.

Authors:
 [1];  [1];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of California, Santa Barbara, CA (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1471867
Report Number(s):
ORNL/LTR-2018/918
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Sokolov, Mikhail A., Chen, Xiang, and Odette, George R. Fracture Toughness Characterization of Highly irradiated Reactor Pressure Weld from the ATR-2 Experiment. United States: N. p., 2018. Web. doi:10.2172/1471867.
Sokolov, Mikhail A., Chen, Xiang, & Odette, George R. Fracture Toughness Characterization of Highly irradiated Reactor Pressure Weld from the ATR-2 Experiment. United States. doi:10.2172/1471867.
Sokolov, Mikhail A., Chen, Xiang, and Odette, George R. Wed . "Fracture Toughness Characterization of Highly irradiated Reactor Pressure Weld from the ATR-2 Experiment". United States. doi:10.2172/1471867. https://www.osti.gov/servlets/purl/1471867.
@article{osti_1471867,
title = {Fracture Toughness Characterization of Highly irradiated Reactor Pressure Weld from the ATR-2 Experiment},
author = {Sokolov, Mikhail A. and Chen, Xiang and Odette, George R.},
abstractNote = {The UCSB ATR-2 irradiation experiment is designed to generate a new database on a wide variety of irradiated reactor pressure vessel (RPV) steels to fill a critical gap in predicting high fluence embrittlement for extended plant operation up to 80 years. A major focus in this experiment is to characterize the effects of irradiation temperature, neutron flux and fluence, and alloy chemistry on MNSP evolution, and model how these features impact hardening and embrittlement, manifested as shifts in ductile-to-brittle transition temperature. As part of these efforts, disk compact tension (DCT) specimens of three representative materials were included in the ATR-2 experiment to have direct measurement of transition fracture toughness shift and, thus, to have some benchmark data to compare outcoming predictive models with actual fracture toughness shifts. In addition, the attempts would be made to use these fracture toughness data to address the potential effect of high dose irradiation on the shape of the Master Curve for highly embrittled RPV material.This report provides data for the fracture toughness characterization of highly embrittled weld from Palisades steam generator.},
doi = {10.2172/1471867},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {8}
}

Technical Report:

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