Molten salt reactor system dynamics in simulink and modelica, a code to code comparison

被引:2
作者
Pathirana, Visura [1 ]
Creasman, Sarah Elizabeth [1 ]
Chvala, Ondrej [1 ,2 ]
Skutnik, Steve [1 ,3 ]
机构
[1] Univ Tennessee, Dept Nucl Engn, Knoxville, TN 37996 USA
[2] Univ Texas Austin, Walker Dept Mech Engn, Austin, TX USA
[3] Oak Ridge Natl Lab, Oak Ridge, TN USA
基金
美国能源部;
关键词
Simulink; Modelica; Molten salt reactor; Dynamics; Multiphysics;
D O I
10.1016/j.nucengdes.2023.112484
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
Understanding reactor dynamics is essential for the development of MSRs. Modern computational software allows rapid development and simulation of multiphysics systems. As such, MSRs can be simulated in various programming languages to study their behavior. Meanwhile, employing various software environments and methods can help ensure that simulation results are accurate and openly accessible to the broader research community. In this publication, two variations of software implementation for an MSR dynamic modeling tool in MATLAB Simulink and OpenModelica are compared. A code-to-code comparison is conducted, and both implementations are benchmarked for accuracy and simulation run time. In addition to the benchmark, a pilot quality assurance program is introduced for the implementation of the OpenModelica model. Finally, a multi-parameter sensitivity analysis is performed to demonstrate possible applications of the Modelica model.
引用
收藏
页数:19
相关论文
共 24 条
  • [1] Asghar Syed Adeel, 2010, Design and Implementation of a User Friendly OpenModelica Graphical Connection Editor, P81
  • [2] Ball S., 1966, Technical Report ORNL-TM-1647
  • [3] Ball S.J., 1965, ORNL -TM-1070
  • [4] Ball S.J., 1964, ISA T, V3, P38
  • [5] Modeling and simulation functional needs for molten salt reactor licensing
    Betzler, Benjamin R.
    Heidet, Florent
    Feng, Bo
    Rabiti, Cristian
    Sofu, Tanju
    Brown, Nicholas R.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2019, 355
  • [6] Sensitivity study of parameters important to Molten Salt Reactor Safety
    Creasman, Sarah Elizabeth
    Pathirana, Visura
    Chvala, Ondrej
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2023, 55 (05) : 1687 - 1707
  • [7] Dolan TJ, 2017, WOODHEAD PUBL SER EN, P1
  • [8] NERTHUS thermal spectrum molten salt reactor neutronics and dynamic model
    Dunkle, Nicholas
    Richardson, Jarod
    Pathirana, Visura
    Wheeler, Alex
    Chvala, Ondrej
    Skutnik, Steven E.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2023, 411
  • [9] Demonstration of the Advanced Dynamic System Modeling Tool TRANSFORM in a Molten Salt Reactor Application via a Model of the Molten Salt Demonstration Reactor
    Greenwood, M. Scott
    Betzler, Benjamin R.
    Qualls, A. Lou
    Yoo, Junsoo
    Rabiti, Cristian
    [J]. NUCLEAR TECHNOLOGY, 2020, 206 (03) : 478 - 504
  • [10] Modified Point-Kinetics Model for Neutron Precursors and Fission Product Behavior for Fluid-Fueled Molten Salt Reactors
    Greenwood, M. Scott
    Betzler, Ben
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 2019, 193 (04) : 417 - 430