In-Reactor Oxidation of Zircaloy-4 Under Low Water Vapor Pressures
Journal Article
·
· Journal of Nuclear Materials
Complementary in- and ex-reactor oxidation tests have been performed to evaluate the oxidation and hydrogen absorption performance of Zircaloy-4 (Zr-4) under relatively low partial pressures (300 and 1000 Pa) of water vapor at specified test temperatures (330° and 370°C). Data from these tests will be used to support fabrication of components intended for isotope-producing targets and provide information regarding the temperature and pressure dependence of oxidation and hydrogen absorption of Zr-4 over the specified range of test conditions. Comparisons between in- and ex- reactor test results were performed to evaluate the influence of irradiation.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-76RL01830
- OSTI ID:
- 1171870
- Report Number(s):
- PNNL-SA-100761; MB0410000; TRN: US1500037
- Journal Information:
- Journal of Nuclear Materials, Vol. 456; ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
ZIRCALOY 4
WATER VAPOR
OXIDATION
Oxygen
HYDROGEN
ABSORPTION
PARTIAL PRESSURE
Pressure Range Pa
Temperature Range 0400-1000 K
COMPARATIVE EVALUATIONS
Temperature Dependence
PRESSURE DEPENDENCE
Radiation Effects
IRRADIATION
Targets
in-reactor
oxidtion
zircaloy
vapor pressure
ZIRCALOY 4
WATER VAPOR
OXIDATION
Oxygen
HYDROGEN
ABSORPTION
PARTIAL PRESSURE
Pressure Range Pa
Temperature Range 0400-1000 K
COMPARATIVE EVALUATIONS
Temperature Dependence
PRESSURE DEPENDENCE
Radiation Effects
IRRADIATION
Targets
in-reactor
oxidtion
zircaloy
vapor pressure