Molten salt cooled encapsulated nuclear heat source (ENHS)-like reactors

被引:7
|
作者
Hong, SG [1 ]
Greenspan, E
机构
[1] Korea Atom Energy Res Inst, Taejon, South Korea
[2] Univ Calif Berkeley, Dept Nucl Engn, Berkeley, CA 94720 USA
关键词
ENHS; molten salt coolant; long life core;
D O I
10.1016/j.pnucene.2005.05.024
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 feasibility of designing molten-salt cooled ENHS (Encapsulated Nuclear Heat Source)-like reactor cores with (PuN)-N-15-(UN)-N-15 nitride fuel for high temperature applications is assessed. The cores considered have uniform fuel composition and no blanket elements and solid reflectors. They are to operate for at least 20 effective full power years without refueling, without fuel shuffling and with burnup reactivity swing less than 0.52%. Three molten-fluoride-salts: NaF(57)-BeF2(43), (LiF)-Li-7(66)-BeF2(34), and LiF(46.5)-NaF(11.5)-KF(42) are considered as the coolant and six materials: SS304, Hastelloy-N, HT-9, Mn-316SS, PCA, and SiC, are considered for the structures. It is found that, neutronically, ENHS-like cores can be designed for all combinations of molten-salt coolants and structural materials considered. Relative to the reference ENHS core, the molten-salt cooled cores require significantly tighter lattice, have softer neutron spectra, significantly more negative Doppler reactivity effect, much more positive coolant temperature and void reactivity effect and smaller reactivity worth of the control elements. Of the molten salts considered, LiF-NaF-KF offers the largest p/d ratio and is most suitable for natural circulation cooling. (C) 2005 Elsevier Ltd. All rights reserved.
引用
收藏
页码:239 / 250
页数:12
相关论文
共 50 条
  • [1] The encapsulated nuclear heat source (ENHS) reactor core design
    Hong, SG
    Greenspan, E
    Kim, YI
    NUCLEAR TECHNOLOGY, 2005, 149 (01) : 22 - 48
  • [2] Power flattening options for the ENHS (Encapsulated Nuclear Heat Source) core
    Hong, SG
    Greenspan, E
    PROGRESS IN NUCLEAR ENERGY, 2005, 47 (1-4) : 178 - 189
  • [3] Heat transfer coefficients for bubbly molten salt nuclear reactors
    Herrera-Hernandez, E. C.
    Perez-Valsecab, A. D.
    Aguilar-Maderac, C. G.
    Vazquez-Rodriguez, A.
    NUCLEAR ENGINEERING AND DESIGN, 2023, 414
  • [4] HEAT CONDUCTION IN INTERNALLY COOLED NUCLEAR REACTORS
    AXFORD, RA
    NUCLEAR SCIENCE AND ENGINEERING, 1958, 4 (02) : 139 - 154
  • [5] Initial calculations for source term of Molten Salt Reactors
    Wheeler, Alexander M.
    Singh, Vikram
    Miller, Laurence F.
    Chvala, Ondrej
    PROGRESS IN NUCLEAR ENERGY, 2021, 132
  • [6] Performance of a gas cooled molten salt heat exchanger
    Qian Jin
    Kong Qiaoling
    Zhang Hongwu
    Huang Weiguang
    Li Wenhui
    APPLIED THERMAL ENGINEERING, 2016, 108 : 1429 - 1435
  • [7] Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors
    Fiorina, Carlo
    ANNALS OF NUCLEAR ENERGY, 2019, 134 : 376 - 382
  • [8] HEAT TRANSFER IN WATER-COOLED NUCLEAR REACTORS
    TONG, LS
    NUCLEAR ENGINEERING AND DESIGN, 1967, 6 (04) : 301 - &
  • [9] Container Materials for Molten Salt Nuclear Reactors: Problems and Research
    Abalin, A. S.
    Abalin, S. S.
    Ivliev, P. N.
    Ignatyev, V. V.
    Klimov, K. S.
    Subbotin, A. S.
    Surenkov, A. I.
    Trunkin, I. N.
    Uglov, V. S.
    PHYSICS OF ATOMIC NUCLEI, 2024, 87 (08) : 1166 - 1175
  • [10] Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors
    Wang, Cheng-Long
    Qin, Hao
    Zhang, Da-Lin
    Tian, Wen-Xi
    Su, Guang-Hui
    Qiu, Sui-Zheng
    NUCLEAR SCIENCE AND TECHNIQUES, 2020, 31 (07)