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, Michael S.; Betzler, Benjamin R.; Qualls, A.L.; Yoo, Junsoo; Rabiti, Cristian

doi:10.1080/00295450.2019.1627124

Cited by 26 publications

(21 citation statements)

References 25 publications

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“…TRANSFORM provides a way to implement system-level conditions including pipe dimensions, pump characteristics, and other details that SCALE cannot. It is based on the object oriented Modelica modeling language (M. S. Greenwood, et al 2020). A simplified flowsheet showing the main components of the MSDR developed in TRANSFORM is given in Figure 4.…”

Section: Transient Simulation Framework Of Reconfigurable Models (Transform)mentioning

confidence: 99%

See 1 more Smart Citation

Molten Salt Reactor Signatures and Modeling Study

Dion

Evans

Croft

et al. 2021

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Section: Transient Simulation Framework Of Reconfigurable Models (Transform)mentioning

confidence: 99%

“…TRANSFORM was also used to investigate the response of the MSDR model to transients in the fuel salt, including addition and removal (M. S. Greenwood, et al 2020). In these simulations the flow rate was kept constant meaning that the additive fuel salt rate was equal to the removal rate.…”

Section: Perturbed Inventory Calculations -Transientsmentioning

confidence: 99%

Molten Salt Reactor Signatures and Modeling Study

Dion

Evans

Croft

et al. 2021

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“…This does neglect the presence of the fuel material on the thermophysical properties of the fluids but is consistent with the approach used in benchmarks performed by other codes. 3,6,7 A comparison of FLiBe at 922 K (1200 F) to historical values for fuel salt used in the MSRE is available in Table 2.1 of Ref. 1 but is also summarized in Table 1 here.…”

Section: Gothic Model Of Msrementioning

confidence: 99%

Steady-State and Transient Benchmarks of GOTHIC to the Molten Salt Reactor Experiment

Harvill¹,

Lane²,

Link³

et al. 2021

Nuclear Technology

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The Molten Salt Reactor Experiment (MSRE), which operated at Oak Ridge National Laboratory from 1965 to 1969, was an experimental reactor that used UF 4 fuel dissolved in molten fluoride salt. Criticality was achieved when the fuel salt mixture passed through the graphite-moderated core region. Therefore, because the fuel and fission products flowed through the system, delayed neutron precursors were not confined to the core, and decay heat was released outside the core, which is a unique challenge relative to more traditional reactor designs with solid fuel. Therefore, research and demonstration reactors such as MSRE have become a valuable source of information for benchmarking modeling and simulation tools for advanced reactor designs. One such tool being considered is GOTHIC, which is a coarse-grid computational fluid dynamics multiphysics software package. GOTHIC includes attributes and physical phenomena needed for modeling these advanced, non-light water reactor designs. For example, GOTHIC includes fluid property tables for various molten salts; a tracer-tracking module for modeling fission products and the radioactive decay and heat release by delayed neutron precursors locally in the fluid outside the core; and other necessary capabilities for modeling molten salt reactor (MSR) designs, including the ability to model dissolved gases. GOTHIC is used to benchmark steady-state and transient conditions from the MSRE. Zero-power physics testing included fuel salt pump start-up and coast-down transients with a control rod automatically moving to maintain criticality. The control rod motion calculated by GOTHIC is a reasonable match to measured data from these transients. Further, low-power testing included a natural convection transient with no control rod motion such that reactor power was responding to heat load demand from the radiator. The reactor power and fuel salt and coolant salt temperatures calculated by GOTHIC exhibit good agreement with measured data. These results confirm GOTHIC capabilities for modeling MSR designs with circulating fuel.

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“…In each progression problem section, any modifications to the underlying model and driving behaviors (e.g., boundary conditions) are described. Additional details regarding the pipe model and treatment of trace substances can be found in Greenwood et al [1]. The TRANSFORM models used to generate the data are included in the TRANSFORM library and can be found at the location of the public repository.…”

Section: Base Transform Modelmentioning

confidence: 99%

“…This fueled salt flows from the core, providing power to the reactor, and then travels to the primary heat exchanger and potentially to other auxiliary systems. This salt-fueled system provides unique challenges to modeling and simulation, as well as licensing and safeguards [1]. As part of an effort to provide methods for tracking, quantifying, and analyzing LF MSRs, this work discusses the chemistry capability that must be integrated into TRANSFORM (Transient Simulation Framework of Reconfigurable Models) [2] to provide more accurate salt composition analysis, especially for dynamic simulations.…”

Section: Introductionmentioning

confidence: 99%

Demonstration of the Advanced Dynamic System Modeling Tool TRANSFORM in a Molten Salt Reactor Application via a Model of the Molten Salt Demonstration Reactor

Cited by 26 publications

References 25 publications

Molten Salt Reactor Signatures and Modeling Study

Molten Salt Reactor Signatures and Modeling Study

Steady-State and Transient Benchmarks of GOTHIC to the Molten Salt Reactor Experiment

Prototype Demonstration of an Integration of a Gibbs Energy Minimizer with TRANSFORM for Molten Salt Reactor Mass Accountancy Studies

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