Verification of the current coupling collision probability method with orthogonal flux expansion for the assembly calculations

Litskevich, Dzianis; Atkinson, Seddon; Davies, Sebastian

doi:10.1016/j.pnucene.2020.103562

Cited by 5 publications

(3 citation statements)

References 11 publications

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“…From a purely neutronic perspective, the SCALE-POLARIS/DYN3D was not able to capture the Considering the multi physics nature of the reactor simulations, the application of the Monte Carlo codes as a neutronics solver is expected to still be time consuming even when applied on the level of a single assembly. Therefore, less general but faster neutron transport solvers should be used for this task (see, for example, [53,54]) and coupled to thermal hydraulics solvers. This approach, in our view, has strong potential to resolve the problems outlined in the present study without involvement of the ADF and SPH factors and other approximations aiming to reduce the naturally inherent error in diffusion approximation.…”

Section: Discussionmentioning

confidence: 99%

A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution

et al. 2021

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High fidelity modelling for nuclear power plant analysis is becoming more common due to advances in modelling software and the availability of high-performance computers. However, to design, develop and regulate new light water nuclear reactors there are, up until now, limited requirements for high fidelity methods due to the already well-established computational methods already being widely accepted. This article explores the additional detail which can be obtained when using high fidelity methods through Monte Carlo/Sub-channel analysis compared to industrial methods of cross-section/nodal analysis using the Advanced Boiling Water Reactor as a case study. This case study was chosen due to the challenges in modelling two phase flow and the high levels of heterogeneity within the fuel assembly design. The article investigates how to implement such an approach, from a bottom-up procedure, by analysing each stage of the modelling process.

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Section: Discussionmentioning

confidence: 99%

A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution

et al. 2021

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“…Finally, after transferring via itself the fuel parameters from DYN3D to the fuel performance code ENIGMA [46] and vice versa. Full coupled reactor physics at the fuel pin level are delivered by the customized coupling software environment after transferring via itself the cross sections from SCALE to the transport code LO-TUS [47][48][49]. Additionally, after transferring via itself the fuel pin power distributions from LOTUS to CTF and the fuel cells feedback distributions from CTF to LOTUS.…”

Section: Introductionmentioning

confidence: 99%

DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part II)

et al. 2022

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Traditionally, the complex coupled physical phenomena in nuclear reactors has resulted in them being treated separately or, at most, simplistically coupled in between within nuclear codes. Currently, coupling software environments are allowing different types of coupling, modularizing the nuclear codes or multi-physics. Several multiscale and multi-physics software developments for LWR are incorporating these to deliver improved or full coupled reactor physics at the fuel pin level. An alternative multiscale and multi-physics nuclear software development between NURESIM and CASL is being created for the UK. The coupling between DYN3D nodal code and CTF subchannel code can be used to deliver improved coupled reactor physics at the fuel pin level. In the current journal article, the second part of the DYN3D and CTF coupling was carried out to analyse a parallel two-way coupling between these codes and, hence, the outer iterations necessary for convergence to deliver verified improved coupled reactor physics at the fuel pin level. This final verification shows that the DYN3D and CTF coupling delivers improved effective multiplication factors, fission, and feedback distributions due to the presence of crossflow and turbulent mixing.

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“…Nodal codes such as DYN3D [17,34] provide simplified coupled reactor physics at the fuel assembly level and the fuel pin power reconstruction required for simplified coupled reactor physics at the fuel pin level as well as the boundary conditions used in other codes. Neutron transport codes such as LOTUS [14,55] (Liverpool Transport Solver) provide full neutronics at the fuel pin level and the boundary conditions used in other codes. Subchannel codes such as CTF [20,50] provide full thermal hydraulics at the fuel pin level and the boundary conditions used in other codes.…”

Section: Introductionmentioning

confidence: 99%

DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)

et al. 2021

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Understanding and optimizing the relation between nuclear reactor components or physical phenomena allows us to improve the economics and safety of nuclear reactors, deliver new nuclear reactor designs, and educate nuclear staff. Such relation in the case of the reactor core is described by coupled reactor physics as heat transfer depends on energy production while energy production depends on heat transfer with almost none of the available codes providing full coupled reactor physics at the fuel pin level. A Multiscale and Multiphysics nuclear software development between NURESIM and CASL for LWRs has been proposed for the UK. Improved coupled reactor physics at the fuel pin level can be simulated through coupling nodal codes such as DYN3D as well as subchannel codes such as CTF. In this journal article, the first part of the DYN3D and CTF coupling within the Multiscale and Multiphysics software development is presented to evaluate all inner iterations within one outer iteration to provide partially verified improved coupled reactor physics at the fuel pin level. Such verification has proven that the DYN3D and CTF coupling provides improved feedback distributions over the DYN3D coupling as crossflow and turbulent mixing are present in the former.

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Verification of the current coupling collision probability method with orthogonal flux expansion for the assembly calculations

Cited by 5 publications

References 11 publications

A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution

A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution

DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part II)

DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)

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