Analysis of accidents and abnormal transients of a high breeding fast reactor cooled by supercritical-pressure light water

Rui Guo; Akifumi Yamaji; Yoshiaki Oka

doi:10.1016/j.nucengdes.2015.08.023

Analysis of accidents and abnormal transients of a high breeding fast reactor cooled by supercritical-pressure light water

Rui Guo^*, Akifumi Yamaji, Yoshiaki Oka

^*Corresponding author for this work

Research output: Contribution to journal › Article › peer-review

1 Citation (Scopus)

Abstract

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.

Original language	English
Pages (from-to)	228-238
Number of pages	11
Journal	Nuclear Engineering and Design
Volume	295
DOIs	https://doi.org/10.1016/j.nucengdes.2015.08.023
Publication status	Published - 2015 Dec 15

ASJC Scopus subject areas

Nuclear Energy and Engineering
Mechanical Engineering
Safety, Risk, Reliability and Quality
General Materials Science
Nuclear and High Energy Physics
Waste Management and Disposal

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10.1016/j.nucengdes.2015.08.023

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AB - 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.

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Analysis of accidents and abnormal transients of a high breeding fast reactor cooled by supercritical-pressure light water

Abstract

ASJC Scopus subject areas

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