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Title: Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation

Abstract

An out-of-reactor method for screening to predict relative in-reactor hydriding behavior of zirconium-based materials is disclosed. Samples of zirconium-based materials having different compositions and/or fabrication methods are autoclaved in a relatively concentrated (0.3 to 1.0M) aqueous lithium hydroxide solution at constant temperatures within the water reactor coolant temperature range (280 to 316 C). Samples tested by this out-of-reactor procedure, when compared on the basis of the ratio of hydrogen weight gain to oxide weight gain, accurately predict the relative rate of hydriding for the same materials when subject to in-reactor (irradiated) corrosion. 1 figure.

Inventors:
; ; ; ;
Issue Date:
OSTI Identifier:
7167792
Patent Number(s):
4916076 A
Application Number:
PPN: US 7-208332
Assignee:
Battelle Memorial Inst., Richland, WA (United States) PTO; EDB-94-116433
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Patent
Resource Relation:
Patent File Date: 17 Jun 1988
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ZIRCONIUM ALLOYS; HYDRIDATION; HYDROGEN EMBRITTLEMENT; RADIATION EFFECTS; FORECASTING; MATERIALS TESTING; REACTOR MATERIALS; WATER COOLED REACTORS; ALLOYS; CHEMICAL REACTIONS; EMBRITTLEMENT; MATERIALS; REACTORS; TESTING; 360106* - Metals & Alloys- Radiation Effects; 360105 - Metals & Alloys- Corrosion & Erosion; 360103 - Metals & Alloys- Mechanical Properties; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Johnson, A.B. Jr., Levy, I.S., Trimble, D.J., Lanning, D.D., and Gerber, F.S. Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation. United States: N. p., 1990. Web.
Johnson, A.B. Jr., Levy, I.S., Trimble, D.J., Lanning, D.D., & Gerber, F.S. Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation. United States.
Johnson, A.B. Jr., Levy, I.S., Trimble, D.J., Lanning, D.D., and Gerber, F.S. Tue . "Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation". United States.
@article{osti_7167792,
title = {Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation},
author = {Johnson, A.B. Jr. and Levy, I.S. and Trimble, D.J. and Lanning, D.D. and Gerber, F.S.},
abstractNote = {An out-of-reactor method for screening to predict relative in-reactor hydriding behavior of zirconium-based materials is disclosed. Samples of zirconium-based materials having different compositions and/or fabrication methods are autoclaved in a relatively concentrated (0.3 to 1.0M) aqueous lithium hydroxide solution at constant temperatures within the water reactor coolant temperature range (280 to 316 C). Samples tested by this out-of-reactor procedure, when compared on the basis of the ratio of hydrogen weight gain to oxide weight gain, accurately predict the relative rate of hydriding for the same materials when subject to in-reactor (irradiated) corrosion. 1 figure.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {4}
}