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Neutron Embrittlement Analysis of Qinshan 320MWe RPV on OLE

[+] Author Affiliations
Tao Hongxin, He Yinbiao, Cao Ming, Shen Rui

Shanghai Nuclear Engineering Research and Design Institute, Shanghai, China

Paper No. ICONE25-66361, pp. V001T01A013; 4 pages
doi:10.1115/ICONE25-66361
From:
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5779-3
  • Copyright © 2017 by ASME

abstract

One of the fundamental requirements on nuclear safety is to prevent the radioactive material from being released. Therefore, it is paramount to maintain the structural integrity of the pressure boundary of the reactor coolant system. The reactor pressure vessel (RPV), under high temperature, high pressure and high radiation in operation, is the most important as well as a Class I nuclear safety equipment. For a pressurized water reactor (PWR), the life of the RPV determines the service life of the entire nuclear power plant. The key factor controlling the life of a RPV is the accumulation of the neutron flux and which induces irradiation embrittlement degrading the anti-fracture capability of the RPV material. Several anti-fracture capability assessments carried out for the Qinshan 320MWe (QS1) RPV, such as (a) the structural integrity assessment against pressurized thermal shocks; (b) the fracture mechanics assessment under irradiation; (c) the P-T limit curves revised; (d) the evaluation of USE. They all demonstrated that the structural integrity of the QS1 RPV would be maintained for the extended service life.

Copyright © 2017 by ASME

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