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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-bsed materials is disclosed. Samples of zirconium-based materials having different composition and/or fabrication 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.degree. to 316.degree. 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 hyriding for the same materials when subject to in-reactor (irradiated) corrision.

Inventors:
 [1];  [2];  [2];  [2];  [1]
  1. (Richland, WA)
  2. (Kennewick, WA)
Publication Date:
Research Org.:
Pacific Northwest National Laboratory (PNNL), Richland, WA
OSTI Identifier:
867334
Patent Number(s):
US 4916076
Assignee:
Battelle Memorial Institute (Richland, WA) PNNL
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
method; predict; relative; hydriding; zirconium; alloys; nuclear; irradiation; out-of-reactor; screening; in-reactor; behavior; zirconium-bsed; materials; disclosed; samples; zirconium-based; composition; fabrication; autoclaved; relatively; concentrated; 0m; aqueous; lithium; hydroxide; solution; constant; temperatures; water; reactor; coolant; temperature; range; 280; degree; 316; tested; procedure; compared; basis; ratio; hydrogen; weight; oxide; accurately; rate; hyriding; subject; irradiated; corrision; lithium hydroxide; coolant temperature; constant temperature; water reactor; zirconium alloy; reactor coolant; temperature range; zirconium alloys; hydroxide solution; reactor method; accurately predict; oxide solution; predict relative; /436/73/376/

Citation Formats

Johnson, Jr., A. Burtron, Levy, Ira S., Trimble, Dennis J., Lanning, Donald D., and Gerber, Franna S.. Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation. United States: N. p., 1990. Web.
Johnson, Jr., A. Burtron, Levy, Ira S., Trimble, Dennis J., Lanning, Donald D., & Gerber, Franna S.. Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation. United States.
Johnson, Jr., A. Burtron, Levy, Ira S., Trimble, Dennis J., Lanning, Donald D., and Gerber, Franna S.. Mon . "Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation". United States. https://www.osti.gov/servlets/purl/867334.
@article{osti_867334,
title = {Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation},
author = {Johnson, Jr., A. Burtron and Levy, Ira S. and Trimble, Dennis J. and Lanning, Donald D. and Gerber, Franna S.},
abstractNote = {An out-of-reactor method for screening to predict relative in-reactor hydriding behavior of zirconium-bsed materials is disclosed. Samples of zirconium-based materials having different composition and/or fabrication 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.degree. to 316.degree. 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 hyriding for the same materials when subject to in-reactor (irradiated) corrision.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {1}
}

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