Research on the on-line fracture assessment of cracked primary loop pipes in NPPs

Author:

Chen Mingya,Gao Hongbo,Lin Lei,Xu Decheng,Zhou Shuai,Wang Weiqiang,Shi Jinhua,Peng Qunjia,Chen Zhilin

Funder

National Key Research and Development Program of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference21 articles.

1. ANSYS. ANSYS release documents, Rev. 2020.Canonsburg, ANSYS, 2020.

2. ASME. ASME boiler and pressure vessel code Sec.III Rules for construction of nuclear facility components.Washington D C, The American society of mechanical engineers, 2018, 52-551.

3. Formulation of three-dimensional Green's function and its application to fatigue life evaluation of pressurizer key engineering materials;Chang;Nucl. Eng. Technol.,2006

4. Chen, M.Y., Yu, M., Zhang, Y.Z., etc. Study on stress-based fatigue monitoring methodology for class 1 nuclear pipe based on the RCC-M Code. Nucl. Eng. Design, under review.

5. The probabilistic structural integrity assessment of reactor pressure vessels under pressurized thermal shock loading;Chen;Nucl. Eng. Des.,2015

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