Fracture analysis of the limit a curve for reactor integrity subjected to pressurized thermal shock (pts)

S. Q. Gao; K. K. Shi; H. Xie; N. B. Jiang; L. P. Zhang; Y. C. Lu; Z. X. Zeng

Fracture analysis of the limit a curve for reactor integrity subjected to pressurized thermal shock (pts)

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SMiRT-24_02-03-01.pdf (1.01 MB)

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2017-08-20

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02 - Fracture Mechanics and Structural Integrity
02-03 - Nuclear Piping / PTS / RPV Integrity III
00 - SMiRT 24 - Busan, Republic of Korea. August 20-25, 2017

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IASMiRT

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http://www.lib.ncsu.edu/resolver/1840.20/35848

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2017 - SMiRT 24 - Busan, Republic of Korea

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Fracture analysis of the limit a curve for reactor integrity subjected to pressurized thermal shock (pts)

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