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Improvement of SAMPSON Code for BWR Severe Accident Analysis

[+] Author Affiliations
Maolong Liu, Yuki Ishiwatari, Koji Okamoto

The University of Tokyo, Tokyo, Japan

Paper No. ICONE21-16719, pp. V006T15A021; 9 pages
doi:10.1115/ICONE21-16719
From:
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 6: Beyond Design Basis Events; Student Paper Competition
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5583-6
  • Copyright © 2013 by ASME

abstract

The SAMPSON code has been developed in the IMPACT project in Japan to investigate severe accident phenomena for light water reactors. It integrates various analysis modules into a single code. The authors improved the fuel rod heat-up module of SAMPSON code by modeling the oxidation reaction of various core structures, including Zircaloy, stainless steel and B4C. And the creep failures of the Zircaloy fuel cladding and stainless steel monitoring guide tubes of the source range monitor (SRM) in the reactor core was also modeled for severe accident analysis.

Copyright © 2013 by ASME

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