An experimental testing of coolant flow rate and velocity in the core of Nigeria Research Reactor-1

被引:0
作者
Physics Department, Ahmadu Bello University, Zaria, Nigeria [1 ]
不详 [2 ]
不详 [3 ]
机构
[1] Physics Department, Ahmadu Bello University, Zaria
[2] Centre for Energy Research and Training, Ahmadu Bello University, Zaria
[3] CAAS Mando, Division of Agricultural Colleges, Ahmadu Bello University, Zaria
来源
Int. J. Nucl. Energy Sci. Technol. | / 2卷 / 171-185期
关键词
Core; Flow rate; NIRR-1; Reactor; Thermo-hydraulic;
D O I
10.1504/IJNEST.2015.071627
中图分类号
学科分类号
摘要
This paper describes experiments to understand the behaviour of nuclear reactors' thermo-hydraulic parameters allow improved model predictions, contributing to their safety. The Nigeria Miniature Neutron Source Reactor called Nigeria Research Reactor-1 (NIRR-1) is a tank-in-pool type reactor with 90.2% enriched uranium as fuel, and light water as moderator and coolant. The core is cooled by light water natural convection. The reactor core assembly, surrounded by beryllium reflectors, is located at the bottom of the reactor vessel. The NIRR-1 has no installed device to measure the core mass flow rate. In this work, experiments were performed at different power levels to monitor some thermo-hydraulic parameters like core mass flow rate, coolant velocity, mass flux, density and Reynolds number in the core of NIRR-1. These experiments confirm the efficiency of natural circulation in removing the heat produced in the reactor core by nuclear fission. Copyright © 2015 Inderscience Enterprises Ltd.
引用
收藏
页码:171 / 185
页数:14
相关论文
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