open access publication

Article, 2024

Application of Modelica/TRANSFORM to system modeling of the molten salt reactor experiment

Nuclear Engineering and Design, ISSN 1872-759X, 0029-5493, Volume 416, Page 112768, 10.1016/j.nucengdes.2023.112768

Contributors

Fischer, Lorenz (Corresponding author) [1] [2] Bureš, Lubomír 0000-0001-6204-0938 [2]

Affiliations

  1. [1] Technical University of Munich
  2. [NORA names: Germany; Europe, EU; OECD];
  3. [2] Seaborg Technologies ApS, Titangade 11, Copenhagen, 2200, Denmark
  4. [NORA names: Denmark; Europe, EU; Nordic; OECD]

Abstract

The molten salt reactor (MSR), being a liquid-fueled reactor, exhibits a strong coupling between neutronics and thermal hydraulics originating from the simultaneous utilization of the fuel as the coolant. Analysis of the dynamic behavior of MSRs thus necessitates the use of coupled multiphysics tools. This work leverages the multiphysics capabilities of the Modelica-based, open-source component library Transient Simulation Framework of Reconfigurable Modules (TRANSFORM) and demonstrates its ability to simulate the behavior of an MSR with the focus on modeling the Molten Salt Reactor Experiment (MSRE). The model employs 1D thermal-hydraulic components with a coarse radial and axial discretization of the active core region approximating the design of the MSRE. The power generation within each node is determined by neutron point kinetics which are modified to account for the effects of fuel circulation. Using the developed model, neutronic and thermal-hydraulic behavior under steady-state conditions is characterized and compared to experimental data and alternative computational codes. Some discrepancies are found but most of them are explained by the modeling choices and uncertainties in input data. Performance of the model under transient conditions is then investigated by simulating experiments conducted on the MSRE; the results are again benchmarked against reference data. Overall, good agreement is attained.

Keywords

Molten Salt Reactor Experiment, Multiphysics tool, active core region, analysis, applications, axial discretization, behavior, capability, choice, circulation, code, compared to experimental data, components, computer code, conditions, coolant, core region, coupling, data, design, development model, discrepancy, discretization, dynamic behavior, effect, experimental data, experiments, framework, fuel, fuel circulation, generation, hydraulic, input, input data, kinetics, liquid fuel reactors, model, model choice, molten, molten salt reactor, multiphysics, multiphysics capabilities, neutron, neutron point kinetics, nodes, performance, point kinetics, power, power generation, reactor, reactor experiments, region, results, salt reactor, simulation framework, simultaneous utilization, steady-state conditions, system model, thermal-hydraulic behavior, thermal-hydraulic components, thermal-hydraulics, tools, transformation, transient conditions, transient simulation framework, uncertainty, utilization

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