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

• 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
• Chủ đề: 1. 21 specific nuclear reactors and associated plants; 2. 36 materials science; 3. Atomic displacements; 4. Fuel cans; 5. Protons

Tóm tắt

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.