Summary of researches on operational characteristics and safety of molten salt fast reactors based on neutronics and thermal-hydraulics coupling analysis

被引:0
|
作者
Mochizuki, Hiroyasu [1 ]
机构
[1] Beyond Energy R&D Association (BERD), 1-7-6, Toranomon, Minato-ku, Tokyo,105-0001, Japan
关键词
Berkelium - Californium - Fuel storage - Gas fuel purification - Lawrencium - Light water reactors - Mendelevium - Molten salt reactor - Nuclear engineering - Plutonium compounds - Reactor refueling - Reactor shielding - Reactor startup - Void fraction;
D O I
10.1016/j.nucengdes.2025.113941
中图分类号
学科分类号
摘要
The present paper mainly summarizes the operational and safety characteristics found by the neutronics and thermal-hydraulics coupling analysis for molten-salt fast reactors (MFR). Analysis methods for MFRs have been developed using system codes and Computational Fluid Dynamics (CFD) codes. Traditionally, the analysis has been limited to single-phase flow of the molten fuel salt, but recently analysis has been conducted under two-phase flow conditions with a small amount of helium gas injected to remove fission products (FP). In the MSFR developed by the EU, the void fraction due to two-phase flow is locally distributed, and a method for analyzing this by coupling advanced neutronics calculation methods with a CFD code has been proposed. On the other hand, a method that models all heat transport systems using a system code with reactor point kinetic (PRK) models have also been proposed. In this case, a CFD code is also used to calculate the precise behavior of flow scheme in the reactor. Since MFRs generally do not have control rods, the method of starting up the reactor must be different from that of light water reactors (LWR). Various methods have been proposed, but this paper introduces a startup method that takes advantage of the characteristics of two-phase flow and its negative reactivity. In the analysis of load-following operation, several methods have been proposed to perform time-order load-following operation by actively varying the reactor power, as in conventional LWRs. Recently, a passive load-following operation method has been proposed that fully exploits the characteristics of MFR. In this passive method, the reactor is operated to respond naturally to temperature changes in the heat transport system caused by flow rate changes corresponding to load variations in the energy conversion system, without controlling the fuel and intermediate circuits. This operation method introduces a heat storage tank in the intermediate circuit, which allows load-following operation in all modes from long to short duration. With regard to safety, the paper presents examples of system code and CFD code analysis of the behavior with a safety protection system bypassed for various transients in two-phase flow conditions. These analyses show that molten salt fast reactors always transition to the safe operating range after transients. © 2025 Elsevier B.V.
引用
收藏
相关论文
共 50 条
  • [1] CODE DEVELOPMENT FOR THE NEUTRONICS/THERMAL-HYDRAULICS COUPLING TRANSIENT ANALYSIS OF MOLTEN SALT REACTORS
    Hu, Tianliang
    Cao, Liangzhi
    Wu, Hongchun
    Zhuang, Kun
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 3, 2017,
  • [2] Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors
    Qiu, S.
    Zhang, D.
    Liu, L.
    Liu, M.
    Xu, R.
    Gong, C.
    Su, G. H.
    KERNTECHNIK, 2016, 81 (02) : 149 - 159
  • [3] Fuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations
    Zhou, Shengcheng
    Yang, Won Sik
    Park, Tongkyu
    Wu, Hongchun
    ANNALS OF NUCLEAR ENERGY, 2018, 114 : 369 - 383
  • [4] Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY
    Hu, Tianliang
    Cao, Liangzhi
    Wu, Hongchun
    Du, Xianan
    He, Mingtao
    ANNALS OF NUCLEAR ENERGY, 2017, 109 : 260 - 276
  • [5] 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
  • [6] 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,
  • [7] NUMERICAL RESEARCH ON STEADY COUPLING OF NEUTRONICS AND THERMAL-HYDRAULICS FOR A MOLTEN SALT REACTOR
    Zhang, Dalin
    Liu, Changliang
    Qian, Libo
    Su, Guanghui
    Qiu, Suizheng
    ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 3, 2008, : 95 - 105
  • [8] Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor
    Mochizuki, Hiroyasu
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2023, 60 (06) : 642 - 668
  • [9] Coupled neutronics and thermal-hydraulics numerical simulations of a Molten Fast Salt Reactor (MFSR)
    Laureau, A.
    Rubiolo, P. R.
    Heuer, D.
    Merle-Lucotte, E.
    Brovchenko, M.
    SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, 2014,
  • [10] Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and the RELAP5-3D code for a molten salt fast reactor
    Mochizuki, Hiroyasu
    NUCLEAR ENGINEERING AND DESIGN, 2020, 368