Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER

Du, Xianan; Tao, Yushan; Zheng, Youqi; Wang, Chenglong; Wang, Yongping; Qiu, Suizheng; Zhang, Bin; Zhai, Zian

doi:10.1016/j.nucengdes.2021.111404

Cited by 11 publications

(2 citation statements)

References 14 publications

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“…The study demonstrated that the core components, such as HPs, matrix, and fuel rods, exhibited significant thermal margins during normal operating conditions, indicating their ability to operate with ample safety margins (Huang et al, 2022). The findings indicated that the core design proposed for the Unmanned Portable Reactor in Silence (UPR-S), which operated on the NUSTER power system, successfully fulfilled the criteria of criticality safety and operational longevity (Du et al, 2021). Nonetheless, in the event of a failure of the two adjacent HPs in the 1/8 reactor core, it had been observed that the temperature of the Molybdenum matrix surpasses its temperature threshold, leading to a notable escalation in average thermal stress.…”

Section: Chinese Hpcr Researchmentioning

confidence: 92%

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: 92%

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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“…The study demonstrated that the core components, such as HPs, matrix, and fuel rods, exhibited significant thermal margins during normal operating conditions, indicating their ability to operate with ample safety margins . The findings indicated that the core design proposed for the Unmanned Portable Reactor in Silence (UPR-S), which operated on the NUSTER power system, successfully fulfilled the criteria of criticality safety and operational longevity (Du et al, 2021). Nonetheless, in the event of a failure of the two adjacent HPs in the 1/8 reactor core, it had been observed that the temperature of the Molybdenum matrix surpasses its temperature threshold, leading to a notable escalation in average thermal stress.…”

Section: Chinese Hpcr Researchmentioning

confidence: 99%

Numerical and Experimental Studies on Small/Micro Nuclear Reactors

2024

Frontiers Research Topics

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