Advanced UZrH research reactor design, part I: thermal-hydraulic review

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2026-06-01 Epub Date: 2026-05-06 DOI:10.1016/j.jandt.2026.05.002

Qifan Yu, Ersheng You, Yiyi Li, Dianchuan Xing, Tianzhou Xie, Liangzi Wang, Lanjiang Zheng, Xianjun Zhang, Zhike Lan

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Abstract

Uranium–Zirconium Hydride (UZrH) research reactor is a type of research reactor that uses UZrH fuel as its core fuel. This reactor type typically employs a pool-type coolant system design, offering advantages such as high inherent safety, versatile applications, simple structure, and flexible operational modes. Internationally, there are numerous design schemes for UZrH research reactors with pool-type configurations, exhibiting significant variations in power levels. This paper reviews the existing coolant systems and accident mitigation measures of pool-type research reactors worldwide. Additionally, it introduces established research reactor designs that incorporate central irradiation channels with dedicated test loops. This paper recommended that the 18 MW UZrH research reactor should adopt a pool-type forced circulation coolant system, and complemented by a passive natural circulation accident mitigation measure. Furthermore, the design should include a central irradiation channel with an independent test loop for neutron flux focusing.

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先进的UZrH研究堆设计，第一部分：热工回顾

铀锆氢化研究堆是一种以铀锆氢化燃料为堆芯燃料的研究堆。该型反应堆通常采用池式冷却剂系统设计，具有固有安全性高、用途广泛、结构简单、运行方式灵活等优点。在国际上，有许多采用池型配置的UZrH研究堆的设计方案，在功率水平上表现出显著的变化。本文综述了世界范围内池式研究堆现有的冷却剂系统和事故缓解措施。此外，它还介绍了已建立的研究反应堆设计，该设计将中央辐照通道与专用测试回路结合起来。建议18mw UZrH研究堆采用池式强制循环冷却系统，辅之以被动自然循环事故缓解措施。此外，设计应包括一个中央辐照通道和一个独立的测试环路，用于中子通量聚焦。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

International Journal of Advanced Nuclear Reactor Design and Technology

CiteScore

2.50

自引率

0.00%

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