首页> 外文会议>International conference on nuclear engineering >THERMAL HYDRAULIC STUDIES OF A FLUORIDE SALT COOLED HIGH TEMPERATURE TEST REACTOR WITH DIFFERENT CFD METHODS
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THERMAL HYDRAULIC STUDIES OF A FLUORIDE SALT COOLED HIGH TEMPERATURE TEST REACTOR WITH DIFFERENT CFD METHODS

机译:不同CFD方法对氟化物盐冷却高温测试反应器的热力学研究

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摘要

The Fluoride-salt-cooled High temperature Reactor (FHR) is new reactor concept-about a decade old which is mainly on going in China and U.S. The preliminary thermal-hydraulic studies of the Fluoride salt cooled High temperature Test Reactor (FHTR) is necessary for the development of the FHR technology. In this paper, the thermal-hydraulics of FHTR (also called TMSR-SF) designed by Shanghai Instituted of Applied Physics (SINAP) is studied in different power modes. The temperature distributions of the coolant and the fuel pebble are obtained using a steady-state thermal-hydraulic analysis code for FHR. The comprehensive local flow and heat transfer are investigated by computational fluid dynamics (CFD) for the locations where may have the maximum pebble temperature based on the results from single channel analysis. The profiles of temperature, velocity, pressure and Nu of the coolant on the surface of the pebble as well as the temperature distribution of a fuel pebble are obtained and analyzed. Numerical results showed that the results of 3-D simulation are in reasonable agreement with that of single channel model and also illustrated safety operation of the preliminary designed TMSR-SF in different power mode.
机译:氟化物盐冷高温反应堆(FHR)是新的反应堆概念,已有大约十年的历史,主要在中国和美国进行。氟化盐盐冷高温试验反应堆(FHTR)的初步热工水力研究是必要的用于FHR技术的发展。本文以不同的功率模式研究了上海应用物理研究所(SINAP)设计的FHTR热工液压油(也称为TMSR-SF)。使用FHR的稳态热工分析代码获得冷却剂和燃料小卵石的温度分布。通过计算流体力学(CFD),根据单通道分析的结果,对卵石温度最高的位置进行全面的局部流动和传热研究。获得并分析了卵石表面上的冷却剂的温度,速度,压力和Nu的分布以及燃料卵石的温度分布。数值结果表明,三维仿真结果与单通道模型的仿真结果基本吻合,并说明了初步设计的TMSR-SF在不同功率模式下的安全运行。

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