Modelling and analysis of the MSFR transient behaviour

Fiorina, Carlo; Lathouwers, D.; Aufiero, Manuele; Cammi, Antonio; Guerrieri, Claudia; Kloosterman, Jan Leen; Luzzi, L.; Ricotti, Marco Enrico

doi:10.1016/j.anucene.2013.08.003

Cited by 69 publications

(39 citation statements)

References 18 publications

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“…thermophysical properties on temperature is one of the important issues in reactor dynamics and safety features. 33 From these results, the accuracy of the models used to describe these properties do have an important impact on sensitivity analysis for the coupling physics on MSR. Figure 6 shows the comparison of sensitivity and sensitivity coefficient in absolute value according to case 1 to 3.…”

Section: 5654e+18mentioning

confidence: 97%

“…Considering updates of salt properties in case 3 increases the importance of coefficients in salt properties. In general, the dependence of molten salt thermophysical properties on temperature is one of the important issues in reactor dynamics and safety features . From these results, the accuracy of the models used to describe these properties do have an important impact on sensitivity analysis for the coupling physics on MSR.…”

Section: Multi‐physics Model Sensitivity Of Molten Salt Reactormentioning

confidence: 99%

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Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor

et al. 2020

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Summary The strongly coupled behaviors between neutronics and thermal‐hydraulics of liquid‐fueled molten salt reactors make it difficult to evaluate system behaviors, due to the transport of precursors along moving fuel. Extending an adjoint‐based method on the multiphysics approach, different assumptions on temperature dependencies of nuclear and thermophysical properties of salt are included in the local sensitivity analysis of a circulating liquid fuel system. Local sensitivity of various types of system response in steady‐state is analyzed for 39 parameters including coupling models, reactor design values, and kinetic constants of delayed neutron and decay heat precursors for a simplified 1D model of molten salt fast reactor. Extended adjoint‐based sensitivity analysis method for MSR is successfully validated achieving 1.38% deviation on average between a recalculation and adjoint method, comparing local sensitivities to all parameters. Also, it takes 66.3 times less in computational time compared with the recalculation method for evaluating the sensitivity of the same type of system response. The importance of all the parameters to the system response is analyzed according to the assumptions on temperature dependencies to nuclear data and salt properties. The most influencing ones are fission energy‐related terms, and their importance increases when temperature dependencies are taken into account, compared with constant properties. Changes of influences on the sensitivity are investigated from the relative changes of the parameter values in various system response types, and it implies the importance to consider the multiphysics modeling on the local sensitivity analysis.

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Section: 5654e+18mentioning

confidence: 97%

Section: Multi‐physics Model Sensitivity Of Molten Salt Reactormentioning

confidence: 99%

Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor

et al. 2020

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“…Various authors have performed a number of steady state and transient multiphysics simulations for the MSFR. A paper by Fiorina et al [9] compares results between models developed on the multiphysics software COMSOL, and coupled in-house codes developed at Delft University of Technology. The models used 2D axisymmetric models of the MSFR and solved multi-group neutron diffusion equations for the neutronics, and they showed good agreement for some of the transient cases studied.…”

Section: Molten Salt Fast Reactormentioning

confidence: 99%

Safety Analysis of Molten Salt Fast Reactor Fuel Composition using Moltres

Park

Rykhlevskii

Huff

2019

Preprint

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The Molten Salt Fast Reactor (MSFR) has garnered much interest for its inherent safety and sustainbility features. The MSFR can adopt a closed thorium fuel cycle for sustainable operation through the breeding of 233 U from 232 Th. The fuel composition changes significantly over the course of its lifespan. In this study, we investigated the steady state and transient behavior of the MSFR using Moltres, a coupled neutronics/thermal-hydraulics code developed within the Multiphysics Object Oriented Simulation Environment (MOOSE) framework. Three different fuel compositions, start-up, earlylife, and equilibrium, were examined for potentially dangerous core temperature excursions during a unprotected loss of heat sink (ULOHS) accident. The six-group and total neutron flux distributions showed good agreement with SERPENT and published MSFR results, while the temperature distribution and total power showed discrepancies which can be attributed to known sources of error. For the transient behavior under the ULOHS scenario, while the transition time towards the new steady state core temperature is also in good agreement with existing MSFR simulations by Fiorina et al., Moltres underestimated the temperature rise by a factor of ten, due to the same sources of error affecting the steady state results. While an MSFR loaded with start-up fuel composition operates at a higher temperature than with the other two fuel compositions, all three cases were shown to be inherently safe due to the strong negative temperature feedback.

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“…The EURATOM 5th Framework Program (MOST project) was carried out to review MSR technology based on MSRE operation experience . The EURATOM 6th, 7th Framework Programs (ALISIA, EVOL projects) were performed to develop MSR as breeders or burners: Molten Salt Actinide Recycler and Transmuter (MOSART) and Molten Salt Fast Reactor (MSFR) . The SPHINX project was implemented in the Czech Republic in 2004 to focus on the development of structural material for thermal spectrum MSR design .…”

Section: Introductionmentioning

confidence: 99%

“…5 The EURATOM 6th, 7th Framework Programs (ALISIA, EVOL projects) were performed to develop MSR as breeders or burners: Molten Salt Actinide Recycler and Transmuter (MOSART) 6 and Molten Salt Fast Reactor (MSFR). 7 The SPHINX project was implemented in the Czech Republic in 2004 to focus on the development of structural material for thermal spectrum MSR design. 8 In Japan, THORIMS-NES concept and several loop experiments were performed by Furukawa for production of fissile U233.…”

Section: Introductionmentioning

confidence: 99%

Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code

et al. 2017

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SummaryA molten salt reactor (MSR) is characterized by simultaneously using liquid fuel salt as both the nuclear fuel and coolant. The redistribution of delayed neutron precursors (DNPs) makes the transient behavior of MSRs different from traditional solid-fuel reactors. In this study, a 3D coupled neutronics/thermal hydraulics code, MOREL2.0, was employed to analyze a liquid-fuel Thorium Molten Salt Reactor (TMSR-LF) under perturbations of fuel pump start-up and coast-down and by overheating and overcooling the inlet fuel temperature. Some transient processes were simulated to provide guidance for the future design and optimization of TMSR-LFs. In response to the perturbations, reactivity was lost and gained in the pump start-up and coast-down, respectively.Overheating the inlet fuel temperature introduced negative reactivity, and TMSR-LF maintained a safety state, while overcooling the inlet fuel temperature resulted in positive reactivity. Overcooling by 70 K produced a supercritical transient condition and a rapid increase in power within a short period, which was followed by a decrease in power due to negative temperature feedback. The transient results demonstrate that the negative temperature feedback coefficients guarantee TMSR-LF inherent safety and the variation range of temperature stay within the safety margin.

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Modelling and analysis of the MSFR transient behaviour

Cited by 69 publications

References 18 publications

Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor

Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor

Safety Analysis of Molten Salt Fast Reactor Fuel Composition using Moltres

Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code

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