Development of multiphysics coupling system for nuclear fuel rod with COMSOL and RMC

Article Nuclear Science & Technology

Supplementing fuel behaviour analyses via coupled Monte Carlo neutronics and fission product solution

Ville Rintala et al.

Summary: To improve the accuracy of fuel behavior codes, researchers developed a coupled calculation system between the Monte Carlo neutronics and burnup calculation solver Serpent and the fuel behavior solver TRANSURANUS. The exchange of data between the solvers included fuel pin axial and radial power and temperature distributions, as well as other parameters. The new capabilities demonstrated small but visible differences when compared to simulations that did not consider fission products calculated by Serpent.

NUCLEAR ENGINEERING AND DESIGN (2022)

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Article Nuclear Science & Technology

Development and application of Monte Carlo and COMSOL coupling code for neutronics/thermohydraulics coupled analysis

Minghui Weng et al.

Summary: The tightly coupled solution of neutronics and thermal-hydraulics is crucial for precise simulation of fuel designs, especially accident tolerant fuel. A new method using MATLAB interface and structured mesh for data interpolation between different meshes was proposed. The verified results show high accuracy and geometric flexibility for multi-physics simulations of different fuel designs.

ANNALS OF NUCLEAR ENERGY (2021)

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Article Nuclear Science & Technology

Development of coupled neutronics and fuel performance analysis capabilities between Serpent and TRANSURANUS

Heikki Suikkanen et al.

NUCLEAR ENGINEERING AND DESIGN (2020)

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Review Materials Science, Multidisciplinary

A review of fuel performance modelling

P. Van Uffelen et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

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Article Nuclear Science & Technology

RMC - A Monte Carlo code for reactor core analysis

Kan Wang et al.

ANNALS OF NUCLEAR ENERGY (2015)

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Article Nuclear Science & Technology

Coupling of system thermal-hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled error

Xu Wu et al.

ANNALS OF NUCLEAR ENERGY (2015)

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Article Nuclear Science & Technology

MOOSE: A parallel computational framework for coupled systems of nonlinear equations

Derek Gaston et al.

NUCLEAR ENGINEERING AND DESIGN (2009)

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Development of multiphysics coupling system for nuclear fuel rod with COMSOL and RMC

Related references

Supplementing fuel behaviour analyses via coupled Monte Carlo neutronics and fission product solution

Development and application of Monte Carlo and COMSOL coupling code for neutronics/thermohydraulics coupled analysis

Development of coupled neutronics and fuel performance analysis capabilities between Serpent and TRANSURANUS

A review of fuel performance modelling

RMC - A Monte Carlo code for reactor core analysis

Coupling of system thermal-hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled error

MOOSE: A parallel computational framework for coupled systems of nonlinear equations

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