In-Reactor Oxidation of Zircaloy-4 Under Low Water Vapor Pressures

Journal Article · Thu Jan 01 00:00:00 EST 2015 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2014.08.053· OSTI ID:1171870

Luscher, Walter G.; Senor, David J.; Clayton, Kevin; Longhurst, Glen

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

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