Contact model analysis on cladding designs against thermal shock for the lower head of central measuring shroud in a fast reactor-Reference-Cited by-同舟云学术

Contact model analysis on cladding designs against thermal shock for the lower head of central measuring shroud in a fast reactor

Published:2019-10 Issue: Volume:352 Page:110204
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Zheng Shu,Lu Daogang,Cao Qiong,Ding Yunlong,Liu Chao

Funder

National Natural Science Foundation of China

Fundamental Research Funds for the Central Universities

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

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2. ASME Boiler and Pressure Vessel Code III. Division 1 – Subsection NH. July 1, 2013.

3. Calculation of thermoplastic stresses of a reactor pressure vessel with cladding from stress-relief annealing up to a thermal shock;Baumjohann;Nucl. Eng. Des.,1986

4. Cladding in RPV integrity and lifetime evaluation;Brumovsky;Procedia Eng.,2015

5. Thermal shock experiments on cracked cladded plates;Hodulak;Nucl. Eng. Des.,1999

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