Study on Thermal-hydraulic Characteristics of Ocean Silent Heat Pipe Cooled Reactor

被引:0
|
作者
Qiu S. [1 ]
Zhang Z. [1 ]
Zhang Z. [1 ]
Wang C. [1 ]
Guo K. [1 ]
Tian W. [1 ]
Su G. [1 ]
机构
[1] School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an
关键词
Conceptual design; Silent heat pipe cooled reactor; System code; Thermal-hydraulic characteristics;
D O I
10.7538/yzk.2022.youxian.0339
中图分类号
学科分类号
摘要
Safe and reliable energy supply is the key foundation for the development of unmanned underwater vehicle (UUV). Unlike land and space missions, underwater missions are more demanding on energy, which requires higher power level, longer operating time, faster response time, and better concealment. Heat pipe cooled reactor has the advantages of large power capacity, simple structure, easy control of reactivity, and rapid thermal response. The solid-state reactor core does not require coolant and relies entirely on heat pipes to dissipate heat, thereby providing good inherent safety, controllability and concealment. Therefore, heat pipe cooled reactor is considered as one of the most promising options for UUV energy supply. In this study, a conceptual design of Nuclear Silent Thermal-Electrical Reactor (NUSTER-100) was proposed to meet the energy requirement of China's heavy ocean UUV research and development. 109 sodium heat pipes were arranged in the reactor core for passive cooling, and the thermoelectric generators (TEGs) were employed in the reactor to convert fission heat to electric power. A set of heat pipe cooled reactor system-wild mathematical and physical models were established, including core neutron physics model, core channel heat transfer model, heat pipe model, thermoelectric conversion model and cold junction heat transfer mode. Based on the efficient and robust numerical algorithm and modular modeling ideas, heat pipe advanced reactor transient analysis code HEART was developed with independent intellectual property rights, and the key modules of HEART were validated and verified by heat pipe experiment and thermoelectric power experiment. The steady-state, cold-start transient and reactivity insertion transient conditions of NUSTER-100 were calculated and analyzed by HEART, and the full power operation characteristics of NUSTER-100 were obtained. Steady-state performance of the NUSTER-100 indicates that the solid-state core has good temperature flattening ability. The surface temperature of the heat pipe is less than 1 300 K, and the average temperature drop of the TEG module in central channel is 724 K, which can produce an electrical power of 1 207.8 W. Based on the cold-start transient thermal-hydraulic analysis, a three-stage heat pipe cooled reactor start-up scheme with high safety was proposed, and the stability and safety of heat pipe reactor under reactivity insertion transient were evaluated. The results show that the three-stage heat pipe cooled reactor start-up scheme can improve the reactor start-up efficiency. This study can provide support for the development of UUV and heat pipe cooled reactor technology in China. © 2022, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:989 / 1004
页数:15
相关论文
共 28 条
  • [1] SHARKH A S M, GRIFFITHS G., Energy storage systems for unmanned underwater vehicles, Underwater Technology, 25, 3, pp. 143-148, (2003)
  • [2] POSTON D I., The heatpipe-operated mars exploration reactor (HOMER), AIP Conference Proceedings, (2001)
  • [3] EL-GENK M S, TOURNIER J M., Conceptual design of HP-STMCs space reactor power system for 110 kWe, Space Technology and Applications, 699, pp. 658-672, (2004)
  • [4] ZHANG Wenwen, LIU Xiao, TIAN Wenxi, Et al., Conceptual design of megawatt class space heat pipe reactor power system, Atomic Energy Science and Technology, 51, 12, pp. 2160-2164, (2017)
  • [5] SUN H, MA P, LIU X, Et al., Conceptual design and analysis of a multipurpose micro nuclear reactor power source, Annals of Nuclear Energy, 121, pp. 118-127, (2018)
  • [6] STERBENTZ J W, WERNER J E, MCKELLAR M G, Et al., Special purpose nuclear reactor (5 MW) for reliable power at remote sites assessment report, (2017)
  • [7] TIAN Z, LIU X, WANG C, Et al., Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor, Nuclear Engineering and Design, 378, (2021)
  • [8] TIAN Z, WANG C, HUANG J, Et al., Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition, Annals of Nuclear Energy, 160, 3, (2021)
  • [9] TIAN Zhixing, LIU Xiao, WANG Chenglong, Et al., Study on heat transfer performance of high temperature potassium heat pipe at steady state, Atomic Energy Science and Technology, 54, 10, pp. 1771-1778, (2020)
  • [10] LI Xiangyue, XIAO Wei, ZHANG Tengfei, Et al., Preliminary research on a multi-physics coupling platform for heat pipe reactors, Nuclear Power Engineering, 42, 2, pp. 208-212, (2021)