Development of coupled neutronics/thermal-hydraulics test case for HPLWR

被引:2
|
作者
Pham, P. [1 ]
Gamtsemlidze, I. D. [1 ]
Bandanovich, R. B. [1 ]
Nikonov, S. P. [1 ]
Smirnov, A. D. [1 ]
机构
[1] Natl Nucl Res Univ MEPhI, Moscow Engn Phys Inst, Dept Theoret & Expt Phys Nucl Reactors, Kashirskoe Shosse 31, Moscow 115409, Russia
关键词
REACTOR; DESIGN;
D O I
10.1088/1742-6596/781/1/012026
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
The High-Performance Light Water Reactor (HPLWR) is the European concept of a supercritical water reactor (SCWR) which is one of the most promising and innovative designs of the Generation IV nuclear reactor concepts. The thermal-hydraulics behavior of supercritical water is significantly different from water at sub-critical pressure because of the difference in the specific heat value. Coupled analysis of HPLWR assembly neutronics and thermal-hydraulics has become important because of the strong influence of the water density on the neutron spectrum and power distribution. Programs MCU (Monte-Carlo Universal) and ATHLET (Analysis of Thermal-hydraulics of Leaks and Transients) were used for better estimation of power and temperature distribution in HPLWR assembly.
引用
收藏
页数:8
相关论文
共 50 条
  • [1] Specifications for a coupled neutronics thermal-hydraulics SFR test case
    Tassone, A.
    Smirnov, A. D.
    Tikhomirov, G. V.
    INTERNATIONAL CONFERENCE FOR YOUNG SCIENTISTS, SPECIALISTS, AND POSTGRADUATES ON NUCLEAR REACTOR PHYSICS 2016 (ICNRP-2016), 2017, 781
  • [2] Development of MCATHAS system of coupled neutronics/thermal-hydraulics in supercritical water reactor
    An, Ping
    Yao, Dong
    Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (06): : 52 - 55
  • [3] DEVELOPMENT OF NEUTRONICS AND THERMAL-HYDRAULICS COUPLED CODE FOR ACCELERATOR DRIVEN SUBCRITICAL SYSTEMS
    Lo, Run
    Wang, Penfei
    Wei, Xinyu
    Revankar, Shripad T.
    Zhao, Fuyu
    PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 4, 2018,
  • [4] Coupled neutronics/thermal-hydraulics for analysis of molten salt reactor
    Guo, Zhangpeng
    Zhou, Jianjun
    Zhang, Dalin
    Chaudri, Khurrum Saleem
    Tian, Wenxi
    Su, Guanghui
    Qiu, Suizheng
    NUCLEAR ENGINEERING AND DESIGN, 2013, 258 : 144 - 156
  • [5] Coupled Neutronics/Thermal-hydraulics for analysis of Molten Salt Reactor
    Guo, Zhangpeng
    Xiao, Yao
    Zhou, Jianjun
    Zhang, Dalin
    Chaudri, Khurrum Saleem
    Qiu, Suizheng
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 4, 2014,
  • [6] Consistent and accurate schemes for coupled neutronics thermal-hydraulics reactor analysis
    Ragusa, Jean C.
    Mahadevan, Vijay S.
    NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (03) : 566 - 579
  • [7] SURVEY OF COUPLING SCHEMES IN TRADITIONAL COUPLED NEUTRONICS AND THERMAL-HYDRAULICS CODES
    Akbas, Sabahattin
    Martinez-Quiroga, Victor
    Aydogan, Fatih
    Ougouag, Abderrafi M.
    Allison, Chris
    PROCEEDINGS OF THE ASME INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2015, VOL 6B, 2016,
  • [8] Full implicit integrate solution to the coupled neutronics/thermal-hydraulics problems
    Han, Zhang
    Fu, Li
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 3, 2014,
  • [9] Challenges in coupled thermal-hydraulics and neutronics simulations for LWR safety analysis
    Ivanov, Kostadin
    Avramova, Maria
    ANNALS OF NUCLEAR ENERGY, 2007, 34 (06) : 501 - 513
  • [10] Development of coupled neutronics/thermal-hydraulics CASIR code system for SCWR core steady state
    Ma, Yong-Qiang
    Chai, Xiao-Ming
    Wang, Yu-Wei
    Pan, Jun-Jie
    An, Ping
    Hedongli Gongcheng/Nuclear Power Engineering, 2013, 34 (01): : 87 - 91