DEVELOPMENT OF A PASSIVE REACTOR SHUTDOWN DEVICE TO PREVENT CORE DISRUPTIVE ACCIDENTS IN FAST REACTORS: A STUDY ON BASIC DEVICE SPECIFICATIONS

Koji Morita, Wei Liu, Tatsumi Arima, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Yuji Arita, Hiroshi Sagara, Masatoshi Kawashima

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

Abstract

A new subassembly-type passive reactor shutdown device is proposed to expand the diversity and robustness of core disruptive accident prevention measures for sodium-cooled fast reactors (SFRs). The device contains pins with a fuel material that is in a solid state during normal operation but melts and fluidizes during an unprotected loss of flow (ULOF) or unprotected transient overpower (UTOP) accident. By rapidly transferring the liquefied device fuel into the lower plenum region of the pins via gravitation alone, the device can passively provide a large negative reactivity to the core. In this study, the nuclear and thermal properties of the device subassembly with metallic fuel were evaluated to determine the basic device specifications for proper device operation during ULOF and UTOP accidents. The results of the transient analysis of the ULOF initiating phase in a 750-MWe-class MOX-fueled SFR core showed that a conventional homogeneous core can maintain stable cooling of the core prior to coolant boiling in the driver fuel subassemblies. On the other hand, the negative reactivity required to terminate the event by device operation was found to be slightly larger in the low sodium void reactivity core than in the conventional homogeneous core.

Original languageEnglish
Title of host publicationSMRs, Advanced Reactors, and Fusion
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Print)9784888982566
DOIs
Publication statusPublished - 2022
Event2022 29th International Conference on Nuclear Engineering, ICONE 2022 - Virtual, Online
Duration: Aug 8 2022Aug 12 2022

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume4

Conference

Conference2022 29th International Conference on Nuclear Engineering, ICONE 2022
CityVirtual, Online
Period8/8/228/12/22

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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