A Safety Enhanced Core Concept for Metal-Fuel Sodium-Cooled Fast Reactors

A safety enhanced metal fuel core has been developed that prevents fuel pin failure and coolant boiling during unprotected loss of flow (ULOF), unprotected transient over power (UTOP) and unprotected loss of heat sink (ULOHS) without relying on radial expansion reactivity.Specifically, we have enhanced inherent reactivity feedback and added passive shutdown devices without significantly changing core specifications and economic performance.The neutron flux distortion during UTOP situation with the control rod withdrawal and the neutron flux changes around the gas expansion module (GEM) during ULOF transient are also confirmed by improved quasi-static approximations.Both local neutron flux changes lead to a power increase, but even taking them into account, the inherent reactivity feedback and reactivity brought by passive devices in the safety enhanced metal fuel core are sufficient to prevent core damage under ULOF, UTOP and ULOHS conditions.

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Publication Details

Journal
Progress in Nuclear Science and Technology
Published
2025-09-30
DOI
https://doi.org/10.15669/pnst.8.104
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00

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article

A Safety Enhanced Core Concept for Metal-Fuel Sodium-Cooled Fast Reactors

Sho Fuchita, Tsuyoshi Mishima, Hirotaka NAKAHARA, Kazuhiro Fujimata et al.
Progress in Nuclear Science and Technology
Nuclear reactor physics and engineering
article

A Safety Enhanced Core Concept for Metal-Fuel Sodium-Cooled Fast Reactors

Sho Fuchita, Tsuyoshi Mishima, Hirotaka NAKAHARA, Kazuhiro Fujimata, Hirokazu Ohta, Satoshi Takeda, Koji Fujimura
article en

Abstract

A safety enhanced metal fuel core has been developed that prevents fuel pin failure and coolant boiling during unprotected loss of flow (ULOF), unprotected transient over power (UTOP) and unprotected loss of heat sink (ULOHS) without relying on radial expansion reactivity.Specifically, we have enhanced inherent reactivity feedback and added passive shutdown devices without significantly changing core specifications and economic performance.The neutron flux distortion during UTOP situation with the control rod withdrawal and the neutron flux changes around the gas expansion module (GEM) during ULOF transient are also confirmed by improved quasi-static approximations.Both local neutron flux changes lead to a power increase, but even taking them into account, the inherent reactivity feedback and reactivity brought by passive devices in the safety enhanced metal fuel core are sufficient to prevent core damage under ULOF, UTOP and ULOHS conditions.

Progress in Nuclear Science and TechnologyVol. 8(0)
Central Research Institute of Electric Power Industry (JP), Hitachi (Japan) (JP), The University of Osaka (JP)
Ministry of Economy, Trade and Industry
Openalex Percentile: Top 59%
Nuclear reactor physics and engineering
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A Safety Enhanced Core Concept for Metal-Fuel Sodium-Cooled Fast Reactors — Sho Fuchita, Tsuyoshi Mishima, et al. · Progress in Nuclear Science and Technology (2025) | TGRS Research Map | TGRS