Preliminary power transient analysis of the super FR with axially heterogeneous core

Tsutomu Okui*, Akifumi Yamaji

*この研究の対応する著者

研究成果: Conference contribution

抄録

The Super FR is one of the SuperCritical Water cooled Reactor (SCWR) concepts with once-through direct cycle plant system. Recently, new design concept of axially heterogeneous core has been proposed, which consists of multiple layers of MOX and blanket fuels. To clarify the safety performance during power transient, safety analyses have been conducted for uncontrolled control rod (CR) withdrawal and CR ejection at full power. RELAP/SCDAPSIM code was used for the safety analysis. The results show that the peak cladding surface temperature (PCST) is high in the upper MOX fuel layer. It is also shown that axial temperature gradient of cladding greatly increases in a short period. Suppressing such large temperature gradient may be a design issue for the axially heterogeneous core from the viewpoint of ensuring fuel integrity.

本文言語English
ホスト出版物のタイトルInternational Conference on Physics of Reactors
ホスト出版物のサブタイトルTransition to a Scalable Nuclear Future, PHYSOR 2020
編集者Marat Margulis, Partrick Blaise
出版社EDP Sciences - Web of Conferences
ページ1419-1426
ページ数8
ISBN(電子版)9781713827245
DOI
出版ステータスPublished - 2020
イベント2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020 - Cambridge, United Kingdom
継続期間: 2020 3 282020 4 2

出版物シリーズ

名前International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
2020-March

Conference

Conference2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
国/地域United Kingdom
CityCambridge
Period20/3/2820/4/2

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学
  • 安全性、リスク、信頼性、品質管理
  • 核物理学および高エネルギー物理学
  • 放射線

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