Long-term creep rupture behavior of smoothed and notched bar specimens of low-carbon nitrogen-controlled 316 stainless steel (316FR) and their evaluation

Nuclear Engineering and Design - Tập 238 Số 2 - Trang 310-321 - 2008
Yukio Takahashi1, Hiroshi Shibamoto2, Kazuhiko Inoue2
1Central Research Institute of Electric Power Industry, Japan
2The Japan Atomic Power Company, Japan

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Tài liệu tham khảo

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