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ASTM Selected Technical Papers
Zirconium in the Nuclear Industry: 20th International SymposiumAvailable to Purchase
Editor
Suresh K. Yagnik
Suresh K. Yagnik
Symposium Chairperson and STP Editor
1
Electric Power Research Institute (EPRI)
,
Palo Alto, CA,
US
Search for other works by this author on:
Michael Preuss
Michael Preuss
Symposium Chair and STP Editor
2
The University of Manchester Manchester
,
GB
;
Monash University
,
Clayton/Melbourne,
AU
Search for other works by this author on:
ISBN:
978-0-8031-7737-6
No. of Pages:
928
Publisher:
ASTM International
Publication date:
2023

Using hydrogen diffusion couples, Naval Nuclear Laboratory has further investigated the hydride solvus in Zircloy-4. Testing involved more than 100 samples experiencing diffusion anneals conducted over weeks to months under both steady-state and thermal-cycling conditions. Hydrogen concentrations of the diffusion couples following test exposures were determined by LECO analysis techniques. Testing was designed to examine for both the temperature dependence on the solvus and for any hydride volume fraction dependence that might exist on the solvus. The resulting data indicate that the dissolution solvus increases slightly as the hydride volume fraction increases. The apparent hydride volume fraction dependence is judged to result from an increasing self-stress imposed in the material as a result of increasing hydride precipitation.

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