In order to enhance making use of potential capabilities of Tehran research reactor (TRR) as a material test reactor (MTR), a 10-bar fuel test loop is designed to provide required infrastructure to perform irradiation tests on domestic fuels in Tehran research reactor. Tehran research reactor with appropriate neutron flux in irradiation positions in the core can provide required neutron fluence for irradiation tests on nuclear fuels. TRR fuel test loop with a wide range of adjustable coolant flow rate, pressure and temperature, within the range applicable in research reactors, has capability to simulate thermal-hydraulic conditions of various research reactors to perform irradiation tests on research reactors’ fuels under the same condition as the reactor core of concern. This paper presents an introductory to the systems and safety features of the TRR fuel test loop as well as the results of analyses performed to investigate neutronic and thermal-hydraulic safety parameters of TRR core during fuel test loop operation and the results of steady state analysis of the loop.

为了更好地利用德黑兰研究堆 (TRR) 作为材料试验堆 (MTR) 的潜在能力，设计了一个 10 bar 燃料测试回路，以提供所需的基础设施，以对德黑兰研究堆的国内燃料进行辐照测试。德黑兰研究堆在堆芯辐照位置具有适当的中子通量，可为核燃料辐照试验提供所需的中子注量。TRR燃料试验回路，冷却剂流量、压力和温度可调范围大，在研究堆适用范围内，能够模拟各种研究堆的热工水力条件，对研究堆燃料进行辐照试验。条件作为关注的反应堆堆芯。