Thermal-Hydraulic and Neutronic Phenomena Important in Modeling and Simulation of Liquid-Fuel Molten Salt Reactors

被引:11
|
作者
Brown, Nicholas R. [1 ]
Diamond, David J. [2 ]
Bajorek, Stephen [3 ]
Denning, Richard
机构
[1] Univ Tennessee, Knoxville, TN 37996 USA
[2] Brookhaven Natl Lab, Upton, NY 11973 USA
[3] US Nucl Regulatory Commiss, Washington, DC 20555 USA
关键词
Phenomena Identification and Ranking Table; molten salt (cooled) reactors; flouride-salt-cooled high-temperature reactors; advanced reactors;
D O I
10.1080/00295450.2019.1590077
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
We discuss liquid-fuel molten salt (cooled) reactors (MSRs); how they will operate under normal, transient, and accident conditions; and the results of an expert elicitation to determine the corresponding thermal-hydraulic and neutronic phenomena important to understanding their behavior. Identifying these phenomena will enable the U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy, and industry to develop or identify modeling functionalities and tools required to carry out confirmatory and licensing analyses that examine the validity and accuracy of an applicant's calculations and help determine the margin of safety in plant design. The NRC frequently does an expert elicitation using a Phenomena Identification and Ranking Table (PIRT) to identify and evaluate the state of knowledge of important modeling phenomena. However, few details about the design of these reactors and the sequence of events during accidents are known, so the process used was considered a preliminary PIRT. A panel comprising a group of subject matter experts met to define phenomena that would need to be modeled and considered the impact/importance of each phenomenon with respect to specific figures of merit (FoMs) (e.g., salt temperature, velocity, and composition). Each FoM reflected a potential impact on radionuclide release or loss of a barrier to release. The panel considered what the path forward might be with respect to being able to model the phenomenon in a simulation code. Results are explained for both thermal and fast spectrum designs, with an emphasis on the thermal-hydraulic takeaways. It was concluded that compared to light water reactors, the lack of high-pressure operation, energetic break flow, depressurization, and quench front tracking may simplify some aspects of an MSR analysis. However, MSRs have new phenomena both for a license applicant and NRC confirmatory analysis. There is a need for enhanced understanding of physical properties for MSRs that encompass several individual thermophysical properties, including thermal conductivity, viscosity, specific heat, density, optical properties, thermodynamic properties, volatilities, solubilities, etc. Salt composition is closely linked to both these properties and the neutronics of the system. Additionally, the large number of MSR concepts and system designs means that there is wide variation in the potential modeling needs for these systems.
引用
收藏
页码:322 / 338
页数:17
相关论文
共 50 条
  • [1] Neutronic and thermal-hydraulic fuel design for a dual-salt breed-and-burn molten salt reactor
    Kasam, Alisha
    Shwageraus, Eugene
    NUCLEAR ENGINEERING AND DESIGN, 2021, 372
  • [2] The Development of a Thermal-Hydraulic and Nonlinear Dynamic System for Molten Salt Reactors
    Ali, Asif
    Liu, Yong Kuo
    Raza, Waleed
    Nazim, Muhammad
    Ali, Amir
    Hussain, S. Aj Id
    ENGINEERING TECHNOLOGY & APPLIED SCIENCE RESEARCH, 2021, 11 (02) : 7023 - 7028
  • [3] STUDY ON THE COUPLED NEUTRONIC AND THERMAL-HYDRAULIC CHARACTERISTICS OF THE NEW CONCEPT MOLTEN SALT REACTOR
    Wang, Peng
    Qiu, Suizheng
    ICONE17, VOL 4, 2009, : 673 - 679
  • [4] Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor
    Wang, Peng
    Qian, Libo
    Zhang, Dalin
    Tian, Wenxi
    Su, Guanghui
    Qiu, Suizheng
    JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME, 2010, 132 (10):
  • [5] Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid Fuel
    Liu, Limin
    Zhang, Dalin
    Lu, Qing
    Wang, Kunpeng
    Qiu, Suizheng
    PROGRESS IN NUCLEAR ENERGY, 2016, 86 : 1 - 10
  • [6] Investigation on fluctuations in full-size Molten Salt Reactor with coupled neutronic/thermal-hydraulic model
    Wang, Jiangmeng
    Cao, Xinrong
    ANNALS OF NUCLEAR ENERGY, 2016, 92 : 262 - 276
  • [7] Thermal-hydraulic phenomena for water cooled nuclear reactors
    Aksan, N.
    D'Auria, F.
    Glaeser, H.
    NUCLEAR ENGINEERING AND DESIGN, 2018, 330 : 166 - 186
  • [8] Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors
    Hu, Siqin
    Zhou, Chong
    Zhu, Guifeng
    Zou, Yang
    Yu, Xiaohan
    Xue, Shuaiyu
    He Jishu/Nuclear Techniques, 2024, 47 (09):
  • [9] Neutronic and Thermal-Hydraulic Performance Analysis of Helical Cruciform Fuel Rods
    Zhang T.
    Han W.
    Shen P.
    Huang S.
    Wang K.
    Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 : 69 - 74
  • [10] Influence of thermal neutron scattering effect of FLiBe molten salt on neutronic performance of molten salt reactors
    Zhang Z.
    Hu J.
    Chen J.
    Cai X.
    He Jishu/Nuclear Techniques, 2023, 46 (07):