Advanced UZrH Research Reactor design, Part I: thermal-hydraulic review

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.