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).
|ホスト出版物のタイトル||Abstracts of the Pacific Basin Nuclear Conference|
|出版ステータス||Published - 2004|
|イベント||Abstracts of the 14th Pacific Basin Nuclear Conference - Honolulu, HI|
継続期間: 2004 3 21 → 2004 3 25
|Other||Abstracts of the 14th Pacific Basin Nuclear Conference|
|Period||04/3/21 → 04/3/25|
ASJC Scopus subject areas