Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients-Reference-Cited by-同舟云学术

Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients

Published:2023-12 Issue: Volume:194 Page:110067
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Huang Zi-Nan,Li Yun-Xiang^ORCID,Li Song,Xi Bin,Zhang You-Peng,Meng Lu,Wang Di-Si^ORCID,Liu Bo,Gu Long,Peng Tian-Ji,Zhang Lu,Jiang Wei,Wallenius Janne

Funder

Ministry of Science and Technology of the People's Republic of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference18 articles.

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3. American Society of Mechanical Engineers. Boiler and Pressure Vessel Committee. Subcommittee on Construction of Nuclear Facility Components.2019 ASME Boiler and Pressure Vessel Code: An International Code. Rules for Construction of Nuclear Facility Components. Division 1, Subsection NB: Class 1 Components[M]. ASME, 2019.

4. American Society of Mechanical Engineers. Boiler and Pressure Vessel Committee. Subcommittee on Materials. 2019 ASME Boiler and Pressure Vessel Code: An International Code. Materials[M]. ASME, 2019.

5. American Society of Mechanical Engineers. Boiler and Pressure Vessel Committee. Subcommittee on Nuclear Power.2019 ASME Boiler and Pressure Vessel Code: An International Code. Rules for Construction of Nuclear Facility Components. Appendices[M]. ASME, 2019.