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Title: In-Situ Creep Testing Capability for the Advanced Test Reactor

Abstract

An instrumented creep testing capability is being developed for specimens irradiated in Pressurized Water Reactor (PWR) coolant conditions at the Advanced Test Reactor (ATR). The test rig has been developed such that samples will be subjected to stresses ranging from 92 to 350 MPa at temperatures between 290 and 370 °C up to at least 2 dpa (displacement per atom). The status of Idaho National Laboratory (INL) efforts to develop the test rig in-situ creep testing capability for the ATR is described. In addition to providing an overview of in-pile creep test capabilities available at other test reactors, this paper reports efforts by INL to evaluate a prototype test rig in an autoclave at INL’s High Temperature Test Laboratory (HTTL). Initial data from autoclave tests with 304 stainless steel (304 SS) specimens are reported.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
1053965
Report Number(s):
INL/JOU-10-18218
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Journal Article
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 179; Journal Issue: 3
Country of Publication:
United States
Language:
English
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; Creep testing; In-pile instrumentation

Citation Formats

Kim, B G, Rempe, J L, Knudson, D L, Condie, K G, and Sencer, B H. In-Situ Creep Testing Capability for the Advanced Test Reactor. United States: N. p., 2012. Web.
Kim, B G, Rempe, J L, Knudson, D L, Condie, K G, & Sencer, B H. In-Situ Creep Testing Capability for the Advanced Test Reactor. United States.
Kim, B G, Rempe, J L, Knudson, D L, Condie, K G, and Sencer, B H. 2012. "In-Situ Creep Testing Capability for the Advanced Test Reactor". United States.
@article{osti_1053965,
title = {In-Situ Creep Testing Capability for the Advanced Test Reactor},
author = {Kim, B G and Rempe, J L and Knudson, D L and Condie, K G and Sencer, B H},
abstractNote = {An instrumented creep testing capability is being developed for specimens irradiated in Pressurized Water Reactor (PWR) coolant conditions at the Advanced Test Reactor (ATR). The test rig has been developed such that samples will be subjected to stresses ranging from 92 to 350 MPa at temperatures between 290 and 370 °C up to at least 2 dpa (displacement per atom). The status of Idaho National Laboratory (INL) efforts to develop the test rig in-situ creep testing capability for the ATR is described. In addition to providing an overview of in-pile creep test capabilities available at other test reactors, this paper reports efforts by INL to evaluate a prototype test rig in an autoclave at INL’s High Temperature Test Laboratory (HTTL). Initial data from autoclave tests with 304 stainless steel (304 SS) specimens are reported.},
doi = {},
url = {https://www.osti.gov/biblio/1053965}, journal = {Nuclear Technology},
number = 3,
volume = 179,
place = {United States},
year = {Sat Sep 01 00:00:00 EDT 2012},
month = {Sat Sep 01 00:00:00 EDT 2012}
}