Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches

Aufiero, Manuele; Brovchenko, Mariya; Cammi, Antonio; Clifford, Ivor; Geoffroy, Olivier; Heuer, D.; Laureau, Axel; Losa, Mario; Luzzi, L.; Merle, E.; Ricotti, Marco Enrico; Rouch, Herve

doi:10.1016/j.anucene.2013.10.015

Cited by 73 publications

(29 citation statements)

References 24 publications

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“…Then, the neutron flux level is normalized according to the MSFR nominal power generated and temperature distribution in the core region by matching previous work by Aufiero et al 14 To validate the adjoint sensitivity equation, the specific simple form of system response P is firstly evaluated as (30), which it does not have any direct term, ∂R/∂α with P ξ = 1. Local sensitivity of the system response can be expressed as the first derivative of P with respect to α, and it can be calculated by means of three methods: recalculation, direct method, and adjoint method as Equations (31), (32), and (33), respectively. As mentioned in the previous section, it is important to choose a proper value for Δα, which is not too large and not too small to capture the actual changes of responses.…”

Section: Validation Of the Adjoint Sensitivity Methods For Circulatimentioning

confidence: 99%

“…Table shows the specification of the case problem as 1D steady‐state MSFR in normal operation condition. Kinetic constants of neutron precursors, fractions of precursors, β i and corresponding decay constants adopted from JEFF‐3.1 library are listed in Table . The effect of the temperature feedback on reactivity is due to the variation of the nuclear data and changes of salt thermophysical properties.…”

Section: Adjoint‐based Sensitivity Analysis For Circulating Liquid Fumentioning

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: Validation Of the Adjoint Sensitivity Methods For Circulatimentioning

confidence: 99%

Section: Adjoint‐based Sensitivity Analysis For Circulating Liquid Fumentioning

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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“…Instead, the unstructured mesh based multi-physics interface relies on the OpenFOAM mesh file format, which is conceptually very similar to CGNS. Some preliminary work on Serpent-OpenFOAM coupling was described by Aufiero et al (2014a) and Leppänen et al (2014). The work on the interface continues, and the current version of Serpent 2 (update 2.1.19) is capable of reading state-point information and writing power distributions in OpenFOAM format tetra-, hexa-, and polyhedral mesh files.…”

Section: Neutronics -Thermal Hydraulics Couplingmentioning

confidence: 99%

The Numerical Multi-Physics project (NUMPS) at VTT Technical Research Centre of Finland

Leppänen

Hovi

Ikonen

et al. 2015

Annals of Nuclear Energy

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“…This study has been performed in the frame of the Molten Salt Fast Reactor (MSFR) Aufiero et al, 2014;Rouch et al, 2014) neutronics and thermal-hydraulics coupling efforts. The case studied here is a one dimensional geometry reactor composed of a molten salt 7 surrounded by a reflector.…”

Section: Presentationmentioning

confidence: 99%

Transient Fission Matrix: Kinetic calculation and kinetic parameters βeff and Λe

Laureau

Aufiero

Rubiolo

et al. 2015

Annals of Nuclear Energy

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Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches

Cited by 73 publications

References 24 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

The Numerical Multi-Physics project (NUMPS) at VTT Technical Research Centre of Finland

Transient Fission Matrix: Kinetic calculation and kinetic parameters βeff and Λe

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