Published February 1, 2015 | Version v1
Journal article

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

Description

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.

Availability note (English)

Available from: DOI:10.1016/j.jnucmat.2014.08.053

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
456
Journal Page Range
p. 17-22
ISSN
0022-3115

Optional Information

Contract/Grant/Project number
AC05-76RL01830
Funding organization
USDOE (United States)
Secondary number(s)
PNNL-SA--100761; OSTIID--1171870