Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe

Chai, Xiaoyan; Guan, Chaoran; Deng, Jiaolong; Zhang, Tengfei; Liu, Xiaojing

doi:10.1016/j.anucene.2022.109399

Cited by 6 publications

(1 citation statement)

References 16 publications

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“…The residual heat removal system designed for the reactor exhibits a sufficient safety margin to effectively dissipate the decay heat. Furthermore, the study conducted by Chai et al (2022) introduced a conceptual design for a moderated micro nuclear reactor cooled by heat pipe (MHPR). The MHPR concept was built upon a softened neutron spectrum, which had the potential to enhance the utilization of thermal neutrons and reduce fuel inventory.…”

Section: Chinese Hpcr Researchmentioning

confidence: 99%

Review of reactor conceptual design and thermal hydraulic characteristics for heat pipe in nuclear systems

Wang,

Ren,

2023

Front. Energy Res.

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Heat pipe cooled reactors (HPCRs) have broad application prospects due to their advantages, such as high power density, compact structure, lower cost, and easy modular assembly. Numerous countries have engaged in extensive research and development of HPCR conceptual designs. The heat from the reactor is removed by high temperature heat pipes (HTHPs), which generally employ alkali metals as the working fluid, such as potassium, sodium, and lithium. Understanding the thermal-hydraulic performance of HTHPs is essential for the safe and efficient operation of a reactor. Therefore, the objective of this paper is to provide a comprehensive review of HPCR conceptual designs developed by various countries in recent years. The research progress of HTHPs on flow and heat transfer performance is reviewed, with an emphasis on both transient and steady-state characteristics. Research progress, as well as the issues that need to be focused on in future research, are discussed in detail.

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Section: Chinese Hpcr Researchmentioning

confidence: 99%

Review of reactor conceptual design and thermal hydraulic characteristics for heat pipe in nuclear systems

Wang,

Ren,

2023

Front. Energy Res.

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Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel

Guo

et al. 2023

Annals of Nuclear Energy

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Key features and highly effective prediction of complete startup from frozen state for high-temperature heat pipe in heat pipe reactor

Yu,

Liu,

et al. 2024

Applied Thermal Engineering

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Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe

Cited by 6 publications

References 16 publications

Review of reactor conceptual design and thermal hydraulic characteristics for heat pipe in nuclear systems

Review of reactor conceptual design and thermal hydraulic characteristics for heat pipe in nuclear systems

Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel

Key features and highly effective prediction of complete startup from frozen state for high-temperature heat pipe in heat pipe reactor

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