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Title: Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I)

Abstract

The Advanced Test Reactor National Scientific User Facility (ATR NSUF) and Electric Power Research Institute (EPRI) formed an agreement to test representative alloys used as reactor structural materials as a pilot program toward establishing guidelines for future ATR NSUF research programs. This report contains results from the portion of this program established as Phase I (of three phases) that entails baseline fracture toughness, stress corrosion cracking (SCC), and tensile testing of selected materials for comparison to similar tests conducted at GE Global Research. The intent of this Phase I research program is to determine baseline properties for the materials of interest prior to irradiation, and to ensure comparability between laboratories using similar testing techniques, prior to applying these techniques to the same materials after having been irradiated at the Advanced Test Reactor (ATR). The materials chosen for this research are the nickel based super alloy X-750, and nitrogen strengthened austenitic stainless steel XM-19. A spare core shroud upper support bracket of alloy X-750 was purchased by EPRI from Southern Co. and a section of XM-19 plate was purchased by EPRI from GE-Hitachi. These materials were sectioned at GE Global Research and provided to INL.

Authors:
;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
USDOE
OSTI Identifier:
1060986
Report Number(s):
INL/EXT-11-24173
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 36 MATERIALS SCIENCE; Boiling Water Reactor; Crack Growth Rate; Fracture Toughness; Stress Corrosion Cracking; X-750; XM-19

Citation Formats

Jackson, J H, and Teysseyre, S P. Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I). United States: N. p., 2012. Web. doi:10.2172/1060986.
Jackson, J H, & Teysseyre, S P. Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I). United States. doi:10.2172/1060986.
Jackson, J H, and Teysseyre, S P. Mon . "Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I)". United States. doi:10.2172/1060986. https://www.osti.gov/servlets/purl/1060986.
@article{osti_1060986,
title = {Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I)},
author = {Jackson, J H and Teysseyre, S P},
abstractNote = {The Advanced Test Reactor National Scientific User Facility (ATR NSUF) and Electric Power Research Institute (EPRI) formed an agreement to test representative alloys used as reactor structural materials as a pilot program toward establishing guidelines for future ATR NSUF research programs. This report contains results from the portion of this program established as Phase I (of three phases) that entails baseline fracture toughness, stress corrosion cracking (SCC), and tensile testing of selected materials for comparison to similar tests conducted at GE Global Research. The intent of this Phase I research program is to determine baseline properties for the materials of interest prior to irradiation, and to ensure comparability between laboratories using similar testing techniques, prior to applying these techniques to the same materials after having been irradiated at the Advanced Test Reactor (ATR). The materials chosen for this research are the nickel based super alloy X-750, and nitrogen strengthened austenitic stainless steel XM-19. A spare core shroud upper support bracket of alloy X-750 was purchased by EPRI from Southern Co. and a section of XM-19 plate was purchased by EPRI from GE-Hitachi. These materials were sectioned at GE Global Research and provided to INL.},
doi = {10.2172/1060986},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {10}
}

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