Research Progress in Key Thermal-hydraulic Issue of Lead-based Fast Reactor

被引：0
|
作者：
Wei S. [1 ]
Wang C. [1 ]
Tian W. [1 ]
Qiu S. [1 ]
Su G. [1 ]
机构：
[1] School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2019年 / 53卷 / 02期
关键词：
Lead-based fast reactor; Research review; Thermal-hydraulics;
D O I：
10.7538/yzk.2018.youxian.0335
中图分类号：
学科分类号：
摘要：
Lead-based fast reactor (LFR) is one of the most promising types among the Gen Ⅳ nuclear reactors. It has better transmutation and breeding capability, as well as higher passive safety and economical efficiency, and it is easy to be miniaturized. As a result, LFR becomes a major concern in the nuclear industry. In this paper, the main concepts of LFR were concluded. A research tendency on small modular LFR was indicated and the existing challenges were pointed out. There are mainly 5 key thermal-hydraulic issues of LFR, namely the flow dynamics and heat transfer of the coolant, thermal-hydraulic phenomena in reactor core and lead pool, system safety characteristics and some specific thermal-hydraulic phenomena of LFR. The research progress in these 5 issues was analyzed and the current research findings were concluded. Besides, the research tendency and difficulties in each research direction were suggested. This paper can provide useful information for LFR design and thermal-hydraulic analysis. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码：326 / 336
页数：10
相关论文
共 47 条
  • [1] Gromov B.F., Belomitcev Y.S., Yefimov E.I., Use of lead-bismuth coolant in nuclear reactors and accelerator-driven systems, Nuclear Engineering and Design, 173, pp. 207-217, (1997)
  • [2] Orlov V.V., Filin A.I., Lopatkin A.V., Et al., The closed on-site fuel cycle of the Brest reactors, Progress in Nuclear Energy, 47, 1-4, pp. 171-177, (2005)
  • [3] Zrodnikov A.V., Toshinsky G.I., Komlev O.G., Et al., Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors, Progress in Nuclear Energy, 50, 2, pp. 170-178, (2008)
  • [4] Davis C., Herring S., Macdonald P., Et al., Design of an actinide burning, lead-bismuth cooled reactor that produces low cost electricity, (2002)
  • [5] Bortot S., Moisseytsev A., Sienicki J.J., Et al., Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator, Nuclear Engineering and Design, 241, 8, pp. 3021-3031, (2011)
  • [6] Maes D., Mechanical design of the small-scale experimental ADS: MYRRHA, Energy Conversion and Management, 47, 17, pp. 2710-2723, (2006)
  • [7] Alemberti A., Carlsson J., Malambu E., Et al., European lead fast reactor: ELSY, Nuclear Engineering and Design, 241, 9, pp. 3470-3480, (2011)
  • [8] Grasso G., Petrovich C., Mattioli D., Et al., The core design of ALFRED, a demonstrator for the European lead-cooled reactors, Nuclear Engineering and Design, 278, pp. 287-301, (2014)
  • [9] Wu Y., CLEAR-S: An integrated non-nuclear test facility for China lead-based research reactor, International Journal of Energy Research, 40, 14, pp. 1951-1956, (2016)
  • [10] Chen H., Chen Z., Chen C., Et al., Conceptual design of a small modular natural circulation lead cooled fast reactor SNCLFR-100, International Journal of Hydrogen Energy, 41, 17, pp. 7158-7168, (2016)
12345