SYMPOSIA PAPER
Published:
01 January 1977
STP35576S
Embrittlement of Zircaloy-4 by Liquid Cesium at 300°C
SourcePrevious attempts to induce embrittlement of zirconium alloys by cesium at light water power reactor operating temperatures (300 to 350°C) have been unsuccessful, although embrittlement has been observed in the 30 to 225°C temperature range. Thus, although cesium is an abundant fission product, it has been discounted previously as a possible cause of failures of Zircaloy-clad fuel rods. In the present study, reactor-grade Zircaloy-4 tube specimens suffered embrittlement in molten cesium at 300°C as well as at 40°C. However, it appeared that embrittlement occurred only if the cesium had a low oxygen content and was contaminated with a trace of iron.
Author Information
Syrett, BC
Stanford Research Institute, Menlo Park, Calif
Cubicciotti, D
Stanford Research Institute, Menlo Park, Calif
Jones, RL
Stanford Research Institute, Menlo Park, Calif
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Details
Developed by Committee: B10
Pages: 281–294
DOI: 10.1520/STP35576S
ISBN-EB: 978-0-8031-4705-8
ISBN-13: 978-0-8031-0602-4