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Development of Structural Codes for JSFR Based on the System Based Code Concept

[+] Author Affiliations
Tai Asayama, Takashi Wakai, Masanori Ando, Satoshi Okajima, Yuji Nagae, Shigeru Takaya, Takashi Onizawa, Kazuyuki Tsukimori, Masaki Morishita

Japan Atomic Energy Agency, Oarai, Ibaraki, Japan

Paper No. PVP2014-28853, pp. V001T01A064; 6 pages
doi:10.1115/PVP2014-28853
From:
  • ASME 2014 Pressure Vessels and Piping Conference
  • Volume 1: Codes and Standards
  • Anaheim, California, USA, July 20–24, 2014
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-4598-1
  • Copyright © 2014 by ASME

abstract

This paper overviews the current status of the ongoing research and development as well as activities for codification of structural codes for the Japan Sodium Cooled Fast Reactor (JSFR), the demonstration fast reactor which is in the phase of conceptual study. Not only the design and construction code which has been published and updated on a regular basis, codes on welding, fitness-for-service, leak-before-break evaluation as well as the guidelines for structural reliability evaluation are being developed. The basic strategy for the development is to fully take advantage of the favorable technical characteristics associated with sodium-cooled fast reactors; the codes will be developed based on the System Based Code concept, a concept that materializes code rules that are most suitable to the reactor types they are applied to. The above mentioned set of codes are planned to be published from the Japan Society of Mechanical Engineers in 2016.

Copyright © 2014 by ASME

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