Mechanical and Microstructural Characterization of Low-Temperature Neutron Irradiated Zircaloy-4
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:22992082
- Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37830 (United States)
- SHINE Medical Technologies, Monona, WI 53713 (United States)
Zr-based alloys, namely Zircaloy-2, Zircaloy-4, ZIRLO, or M5, have been used in light water reactors (LWRs) as structural materials (cladding, pressure tubes, and etc.). Under irradiation conditions, especially at harsh pressurized water reactor (PWR) conditions, these Zr alloys can undergo embrittlement due to corrosion, hydriding, and irradiation induced stresses. This ultimately leads to the severe degradation of Zr-alloys and increase the probability of fuel failure. While various research efforts have been conducted in developing better Zr-based alloys to withstand these harsh environments, there is a considerable amount of Zr-alloy characteristics, such as change in mechanical properties under irradiation conditions and its relationship to the materials microstructure, that need to be studied. This present study has focused on investigation of mechanical and microstructural properties of Zircaloy-4 under low temperature (80 - 100 deg. C) neutron irradiation conditions. Some of the samples studied were also hydrided to evaluate influence of hydride precipitates in the material. (authors)
- OSTI ID:
- 22992082
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Journal Issue: 1 Vol. 114; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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