Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor

被引：0
|
作者：
Zhao X. [1 ]
Huang Y. [1 ]
Jinguang Z. [1 ]
机构：
[1] CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷 / 05期
关键词：
R&D progress; R&D task; SCWR; Thermal hydraulics;
D O I：
10.13832/j.jnpe.2023.05.0223
中图分类号：
学科分类号：
摘要：
Supercritical water cooled reactor (SCWR) is the only water-cooled reactor among the six advanced reactor types identified by the Generation IV International Forum. Supercritical water has a unique performance in thermal hydraulics due to its utilization as a coolant and unique properties in physical phase. This paper introduces the general requirements of SCWR thermal hydraulics, and describes the basic characteristics of typical thermal hydraulic processes and the main research and development progress at present. Focusing on the SCWR engineering application, this paper puts forward the follow-up research and development tasks and suggestions for future development of SCWR. © 2023 Yuan Zi Neng Chuban She. All rights reserved.
引用
收藏
页码：223 / 231
页数：8
相关论文
共 43 条
  • [1] ZANG J G, YAN X, HUANG S F, Et al., A general method for developing friction factor formulas under supercritical conditions and in different geometries, Annals of Nuclear Energy, 65, pp. 262-271, (2014)
  • [2] pp. 93-99, (2019)
  • [3] JACKSON J D., Some striking features of heat transfer with fluids at pressures and temperatures near the critical point, Proceedings of the International Conference on Energy Conversion and Application, pp. 50-61, (2001)
  • [4] BAE Y Y, KIM H Y., Convective heat transfer to CO2 at a supercritical pressure flowing vertically upward in tubes and an annular channel, Experimental Thermal and Fluid Science, 33, 2, pp. 329-339, (2009)
  • [5] LIU S H, HUANG Y P, LIU G X, Et al., Improvement of buoyancy and acceleration parameters for forced and mixed convective heat transfer to supercritical fluids flowing in vertical tubes, International Journal of Heat and Mass Transfer, 106, pp. 1144-1156, (2017)
  • [6] JACKSON J D, HALL W B., Influences of buoyancy on heat transfer to fluids flowing in vertical tubes under turbulent conditions, Proceedings of the Turbulent Forced Convection in Channels and Bundles, pp. 613-640, (1979)
  • [7] WANG H, BI Q C, YANG Z D, Et al., Experimental and numerical investigation of heat transfer from a narrow annulus to supercritical pressure water, Annals of Nuclear Energy, 80, pp. 416-428, (2015)
  • [8] WANG H, BI Q C, WANG L C., Heat transfer characteristics of supercritical water in a 2 × 2 rod bundle - numerical simulation and experimental validation, Applied Thermal Engineering, 100, pp. 730-743, (2016)
  • [9] 35, 2, pp. 33-36, (2014)
  • [10] 39, 6, pp. 878-884, (2019)
12345