Reduced moderation BWR with advanced recycle system (BARS)

K. Hiraiwa*, K. Yoshioka, M. Akiba, Y. Yamamoto, M. Yamaoka, Shinichi Morooka

*Corresponding author for this work

Research output: Chapter in Book/Report/Conference proceedingConference contribution


The innovative concept for a reduced-moderation spectrum boiling water reactor combined with an advanced fuel cycle system, which is named BARS, has been developed. NUCLEAR DESIGN STUDY The nuclear design study focuses on reduction of void coefficient of tight lattice. Streaming channel concept has been introduced to realize the negative void coefficient. Equilibrium core design analysis based on three-dimensional analysis and transient analysis are included in these analyses. NUCLEAR EXPERIMENTAL STUDY Since there were few benchmarking studies on such reduced-moderation lattice like a BARS, the validation study has been required. Therefore the critical assembly experiment on uranium lattice has been done in TOSHIBA critical assembly (NCA) to validate the accuracy of design calculation. THERMAL HYDRAULIC TEST STUDY The thermal hydraulic test study focuses on the coolability of tight lattice. These experiments have been done in Toshiba's high temperature and high-pressure BWR experimental facility for stability and transient test (BEST).

Original languageEnglish
Title of host publicationAbstracts of the Pacific Basin Nuclear Conference
Number of pages1
Publication statusPublished - 2004
Externally publishedYes
EventAbstracts of the 14th Pacific Basin Nuclear Conference - Honolulu, HI
Duration: 2004 Mar 212004 Mar 25


OtherAbstracts of the 14th Pacific Basin Nuclear Conference
CityHonolulu, HI

ASJC Scopus subject areas

  • Engineering(all)


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