Assessment of Various Candidate Salts Properties for Molten Salt Reactor Application by MCNP Software

被引:0
作者
Petrosyan, Taron [1 ]
Melyan, Elmira [1 ]
Katovsky, Karel [1 ]
机构
[1] Brno Univ Technol, Fac Elect Engn & Commun, Tech 10, Brno 61600, Czech Republic
来源
2020 21ST INTERNATIONAL SCIENTIFIC CONFERENCE ON ELECTRIC POWER ENGINEERING (EPE) | 2020年
关键词
Molten Salt Reactor; MCNP; criticality; thorium; FUEL-CYCLE; FLUORIDE;
D O I
10.1109/epe51172.2020.9269202
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
In the study, the model of Molten Salt Reactor was developed for Monte Carlo N-Particle Transport ill computational code analysis. In the course of work, two main tasks were fulfilled, which are simulation of target material behavior as a neutron convertor (producer) under 800 MeV energy proton beam and criticality calculation of the designed reactor. As a result of analysis through the MCNP software, neutron flux and energy distributions obtained, as well as the value of k(eff) multiplication factor of Molten Salt Reactor for a number of different molten salts compositions assessed.
引用
收藏
页码:400 / 405
页数:6
相关论文
共 15 条
  • [1] [Anonymous], LAUR12013642012 LOS
  • [2] CHEMISTRY AND THERMODYNAMICS OF MOLTEN-SALT REACTOR-FUELS
    BAES, CF
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1974, 51 (01) : 149 - 162
  • [3] Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE
    Betzler, Benjamin R.
    Powers, Jeffrey J.
    Worrall, Andrew
    [J]. ANNALS OF NUCLEAR ENERGY, 2017, 101 : 489 - 503
  • [4] Bowman C. D., 1995, BASIS OBJECTIVES LOS
  • [5] Conlin J. L., 2017, LAUR1730912 LOS AL A, DOI [DOI 10.2172/1411369, 10.2172/1411369]
  • [6] Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium
    Cui, D. Y.
    Li, X. X.
    Xia, S. P.
    Zhao, X. C.
    Yu, C. G.
    Chen, J. G.
    Cai, X. Z.
    [J]. PROGRESS IN NUCLEAR ENERGY, 2018, 104 : 75 - 84
  • [7] Corrosion in the molten fluoride and chloride salts and materials development for nuclear applications
    Guo, Shaoqiang
    Zhang, Jinsuo
    Wu, Wei
    Zhou, Wentao
    [J]. PROGRESS IN MATERIALS SCIENCE, 2018, 97 : 448 - 487
  • [8] EXPERIENCE WITH MOLTEN-SALT REACTOR EXPERIMENT
    HAUBENREICH, PN
    ENGEL, JR
    [J]. NUCLEAR APPLICATIONS AND TECHNOLOGY, 1970, 8 (02): : 118 - +
  • [9] Towards the thorium fuel cycle with molten salt fast reactors
    Heuer, D.
    Merle-Lucotte, E.
    Allibert, M.
    Brovchenko, M.
    Ghetta, V.
    Rubiolo, P.
    [J]. ANNALS OF NUCLEAR ENERGY, 2014, 64 : 421 - 429
  • [10] Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects
    Humphrey, Uguru Edwin
    Khandaker, Mayeen Uddin
    [J]. RENEWABLE & SUSTAINABLE ENERGY REVIEWS, 2018, 97 : 259 - 275