Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor

被引:34
|
作者
Rykhlevskii, Andrei [1 ]
Bae, Jin Whan [1 ]
Huff, Kathryn D. [1 ]
机构
[1] Univ Illinois, Dept Nucl Plasma & Radiol Engn, Urbana, IL 61801 USA
基金
美国国家科学基金会;
关键词
Molten salt reactor; Molten salt breeder reactor; !text type='Python']Python[!/text; Depletion; Online reprocessing; Nuclear fuel cycle; Salt treatment; ANALYSIS CAPABILITIES; CORE PHYSICS; CYCLE; NEUTRONICS;
D O I
10.1016/j.anucene.2019.01.030
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
In the search for new ways to generate carbon-free, reliable base-load power, interest in advanced nuclear energy technologies, particularly Molten Salt Reactors (MSRs), has resurged with multiple new companies pursuing MSR commercialization. To further develop these MSR concepts, researchers need simulation tools for analyzing liquid-fueled MSR depletion and fuel processing. However, most contemporary nuclear reactor physics software is unable to perform high-fidelity full-core depletion calculations for a reactor design with online reprocessing. This paper introduces a Python package, SaltProc, which couples with the Monte Carlo code, SERPENT2 to simulate MSR online reprocessing by modeling the changing isotopic composition of MSR fuel salt. This work demonstrates SaltProc capabilities for a full-core, high-fidelity model of the commercial Molten Salt Breeder Reactor (MSBR) concept and verifies these results to results in the literature from independent, lower-fidelity analyses. (C) 2019 Elsevier Ltd. All rights reserved.
引用
收藏
页码:366 / 379
页数:14
相关论文
共 50 条
  • [41] NEW DEVELOPMENT OF THORIUM MOLTEN-SALT REACTOR SYSTEM
    FURUKAWA, K
    TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1988, 74 (11): : 2080 - 2089
  • [42] A Thorium Molten salt reactor when and where you need it
    Hylko, James M.
    Power, 2019, 163 (05)
  • [43] Reactor protection system testing for the solid fuel thorium molten salt reactor
    Liu, Zhen-Bao
    Liu, Ye
    Liu, Gui-Min
    Hou, Jie
    NUCLEAR SCIENCE AND TECHNIQUES, 2016, 27 (05)
  • [44] Plutonium and Minor Actinides Utilization in Thorium Molten Salt Reactor
    Waris, Abdul
    Aji, Indarta K.
    Novitrian
    Kurniadi, Rizal
    Su'ud, Zaki
    3RD INTERNATIONAL CONFERENCE ON ADVANCES IN NUCLEAR SCIENCE AND ENGINEERING 2011 (ICANSE 2011), 2012, 1448 : 115 - 118
  • [45] Reactor protection system testing for the solid fuel thorium molten salt reactor
    Zhen-Bao Liu
    Ye Liu
    Gui-Min Liu
    Jie Hou
    Nuclear Science and Techniques, 2016, 27 (05) : 154 - 162
  • [46] Reactor protection system testing for the solid fuel thorium molten salt reactor
    Zhen-Bao Liu
    Ye Liu
    Gui-Min Liu
    Jie Hou
    Nuclear Science and Techniques, 2016, 27
  • [47] Dynamic Modeling and Performance Analysis of a Two-Fluid Molten-Salt Breeder Reactor System
    Singh, Vikram
    Lish, Matthew R.
    Wheeler, Alexander M.
    Chvala, Ondrej
    Upadhyaya, Belle R.
    NUCLEAR TECHNOLOGY, 2018, 202 (01) : 15 - 38
  • [49] Large eddy simulation of unsteady flow in gas–liquid separator applied in thorium molten salt reactor
    Jing-Jing Li
    Ya-Lan Qian
    Jun-Lian Yin
    Hua Li
    Wei Liu
    De-Zhong Wang
    Nuclear Science and Techniques, 2018, 29
  • [50] Thorium Molten Salt Reactor:A Safe Way Out for Nuclear Energy
    SONG Jianlan (Staff Reporter)
    Bulletin of the Chinese Academy of Sciences, 2012, 26 (03) : 199 - 203