抄録
A high breeding core of supercritical water cooled fast reactor (Super FBR) is designed with the tightly packed fuel assembly for obtaining a high breeding ratio with negative void reactivity. The coolant volume fraction is substantially smaller than that of the tight lattice fuel assembly in Super FRs. The present study conducted the safety analysis of this reactor for the abnormal transients and accidents at supercritical pressure. The safety system and safety criteria are similar to those of Super FRs. The accident "control rod ejection" gives the highest fuel cladding temperature and the highest peak pressure, although which are still within the limit of safety criteria. The overall results show that all the safety criteria are satisfied at the selected events.
本文言語 | English |
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ページ(範囲) | 228-238 |
ページ数 | 11 |
ジャーナル | Nuclear Engineering and Design |
巻 | 295 |
DOI | |
出版ステータス | Published - 2015 12月 15 |
ASJC Scopus subject areas
- 原子力エネルギーおよび原子力工学
- 機械工学
- 安全性、リスク、信頼性、品質管理
- 材料科学一般
- 核物理学および高エネルギー物理学
- 廃棄物管理と処理