Ion irradiation testing of Improved Accident Tolerant Cladding Materials [electronic resource]

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Tác giả:

Ngôn ngữ: eng

Ký hiệu phân loại: 553.98 Economic geology

Thông tin xuất bản: Washington, D.C. : Oak Ridge, Tenn. : United States. National Nuclear Security Administration ; Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 2014

Mô tả vật lý: Size: 8 p. : , digital, PDF file.

Bộ sưu tập: Metadata

ID: 268316

This report summarizes the results of ion irradiations conducted on two FeCrAl alloys (named as ORNL A&B) for improving the accident tolerance of LWR nuclear fuel cladding. After irradiation with 1.5 MeV protons to ~0.5 to ~1 dpa and 300�C nanoindentations were performed on the cross-sections along the ion range. An increase in hardness was observed in both alloys. Microstructural analysis shows radiation induced defects.
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