Preliminary design and assessment of a heat pipe residual heat removal system for the reactor driven subcritical facility

被引:5
|
作者
Zhang, Wenwen [1 ]
Sun, Kaichao [2 ]
Wang, Chenglong [1 ]
Zhang, Dalin [1 ]
Tian, Wenxi [1 ]
Qiu, Suizheng [1 ]
Su, G. H. [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
[2] MIT, Nucl Reactor Lab, Cambridge, MA 02139 USA
关键词
Molten salt subcritical facility; Heat pipe design; Residual heat removal system; CFD analysis; PRECONCEPTUAL DESIGN;
D O I
10.1016/j.net.2021.06.013
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A heat pipe residual heat removal system is proposed to be incorporated into the reactor driven subcritical (RDS) facility, which has been proposed by MIT Nuclear Reactor Laboratory for testing and demonstrating the Fluoride-salt-cooled High-temperature Reactor (FHR). It aims to reduce the risk of the system operation after the shutdown of the facility. One of the main components of the system is an aircooled heat pipe heat exchanger. The alkali-metal high-temperature heat pipe was designed to meet the operation temperature and residual heat removal requirement of the facility. The heat pipe model developed in the previous work was adopted to simulate the designed heat pipe and assess the heat transport capability. 3D numerical simulation of the subcritical facility active zone was performed by the commercial CFD software STAR CCM thorn to investigate the operation characteristics of this proposed system. The thermal resistance network of the heat pipe was built and incorporated into the CFD model. The nominal condition, partial loss of air flow accident and partial heat pipe failure accident were simulated and analyzed. The results show that the residual heat removal system can provide sufficient cooling of the subcritical facility with a remarkable safety margin. The heat pipe can work under the recommended operation temperature range and the heat flux is below all thermal limits. The facility peak temperature is also lower than the safety limits. (c) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY license (http://creativecommons.org/licenses/by/4.0/).
引用
收藏
页码:3879 / 3891
页数:13
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