Design and analysis of passive residual heat removal system for a new MW-class compact nuclear power system

The heat pipe-cooled reactor is an ideal power source for unmanned underwater vehicles (UUVs) due to its compact design, simple structure, and high safety features. However, a heat sink loss accident may lead to reactor damage, requiring a passive residual heat removal system (PRHRS) for emergency cooling. This study presents a novel compact heat pipe reactor with a PRHRS that uses natural circulation to cool the heat pipes' adiabatic sections. A steady-state CFD simulation optimized the geometry, and a transient analysis code was developed in FORTRAN and validated with CFD results. The findings show a sharp increase in fuel temperature immediately after the accident, followed by a decrease as natural circulation cools the reactor. Throughout the accident, component temperatures stayed within permissible limits, with the maximum fuel and heat pipe temperatures not exceeding 965.13 K and 972.5 K, respectively. No boiling occurred in the PRHRS cooling water. This confirms that the PRHRS effectively removes residual heat, ensuring reactor safety during both steady-state and accident conditions, and lays the groundwork for the design of new MW-class compact heat pipe reactors.

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Publication Details

Journal
Nuclear Engineering and Technology
Published
2025-06-09
DOI
https://doi.org/10.1016/j.net.2025.103746
Primary Topic
Nuclear Engineering Thermal-Hydraulics
Type
article
Field-Weighted Citation Impact
0.00

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Design and analysis of passive residual heat removal system for a new MW-class compact nuclear power system

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Nuclear Engineering and Technology
Nuclear Engineering Thermal-Hydraulics
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Design and analysis of passive residual heat removal system for a new MW-class compact nuclear power system

Jianqiang Shan, Yuan Lü, Bo Zhang, Zhenlan Wang, Junli Gou
article en

Abstract

The heat pipe-cooled reactor is an ideal power source for unmanned underwater vehicles (UUVs) due to its compact design, simple structure, and high safety features. However, a heat sink loss accident may lead to reactor damage, requiring a passive residual heat removal system (PRHRS) for emergency cooling. This study presents a novel compact heat pipe reactor with a PRHRS that uses natural circulation to cool the heat pipes' adiabatic sections. A steady-state CFD simulation optimized the geometry, and a transient analysis code was developed in FORTRAN and validated with CFD results. The findings show a sharp increase in fuel temperature immediately after the accident, followed by a decrease as natural circulation cools the reactor. Throughout the accident, component temperatures stayed within permissible limits, with the maximum fuel and heat pipe temperatures not exceeding 965.13 K and 972.5 K, respectively. No boiling occurred in the PRHRS cooling water. This confirms that the PRHRS effectively removes residual heat, ensuring reactor safety during both steady-state and accident conditions, and lays the groundwork for the design of new MW-class compact heat pipe reactors.

Nuclear Engineering and TechnologyVol. 57(11)
Xi'an Jiaotong University (CN)
Xi’an Jiaotong University, National Key Research and Development Program of China
Affordable and clean energy
Openalex Percentile: Top 83%
Nuclear Engineering Thermal-Hydraulics
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