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Current Status and Development of Core Calculation Methodology for Sodium Cooled Fast Reactor in Mitsubishi

[+] Author Affiliations
Kazumi Ikeda, Hiroyuki Moriwaki

Mitsubishi FBR Systems, Inc., Tokyo, Japan

Wataru Nakazato

Mitsubishi Heavy Industries, Ltd., Kobe, Japan

Paper No. ICONE18-29755, pp. 145-154; 10 pages
doi:10.1115/ICONE18-29755
From:
  • 18th International Conference on Nuclear Engineering
  • 18th International Conference on Nuclear Engineering: Volume 6
  • Xi’an, China, May 17–21, 2010
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4934-7
  • Copyright © 2010 by ASME

abstract

This paper presents current status and development of nuclear calculation methodology for sodium cooled fast reactor in Mitsubishi and two core design codes; an original two dimensional cell/lattice calculation code, PIJHEX and a thermal hydraulic calculation code, MIX-MKII. Mitsubishi Atomic Power Industries, Inc. developed several core design codes for Monju and JOYO and recently this activity continues still further for the next FBR in Japan. It is explained in this paper that the PIJHEX is confirmed to be valid from the comparison of Monte Carlo code and the examination on physical phenomenon in calculation results. Besides, the approach toward design and development of code system in Mitsubishi and MIX-MKII are introduced briefly.

Copyright © 2010 by ASME

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