Coupled unstructured fine-mesh neutronics and thermal-hydraulics methodology using open software: A proof-of-concept

Vasconcelos, Vítor; Santos, Adimir dos; Campolina, Daniel; Theler, Germán; Pereira, Cláubia

doi:10.1016/j.anucene.2018.01.021

Cited by 7 publications

(4 citation statements)

References 20 publications

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“…The results obtained from steady state neutronic calculations are shown in Table 7. shows good agreement with those showed in literature [8].…”

Section: Resultssupporting

confidence: 93%

“…Geometry and mesh First of all, the geometry used was chosen because of its simplicity and possibility to continuous previous work [8]. Also, it's a geometry that allows several tests without wasting time, this means that in general the simulations were rapid.…”

Section: 1mentioning

confidence: 99%

“…Due to spatial neutron flux variation in the nucleus, some fuels are at higher temperatures than others, leading to variations in heating also in water around the pins [9]. In addition, [8], [9] presented part of the methodology used in this work, such as geometry and mesh generation, same CFD code (OpenFOAM with a similar solver), same initial and boundary conditions. The geometry used correspond to a IPR-R1 TRIGA fuel rod surrounded for an amount of water to moderate neutron energy, although symmetry condition was used in part of neutronic domain.…”

Section: Introductionmentioning

confidence: 99%

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One-step coupled calculations (Serpent-OpenFOAM) for a fuel rod of the IPR-R1 triga reactor

et al. 2021

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In this work, a single step of coupled calculations for a fuel rod of IPR-R1 TRIGA was performed. The used me-thodology allowed to simulate the fuel pin behavior in steady-state mode for different power levels. The aim of this paper is to present a practical approach to perform coupled calculations between neutronic (Monte Carlo) and thermal-hydraulic (CFD) codes. For this purpose, is necessary to evaluate the influence of the water thermal-physical properties temperature variations on keff parameter. Besides that, Serpent Nuclear Code was used for the neutronics evaluation, while OpenFOAM was used for thermal-hydraulics. OpenFOAM si- mula-tions were made by using a modified chtMultiRegionFoam solver, developed to read Serpent output correctly. The neutronic code was used without any modifications. The results shows that this coupled calculations were consistent and that leads to encouraging further methodology development and its use for full core simulation. Also, the results shows good agreement with calculations performed using other version of OpenFOAM and Milonga as neutronic code.

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“…The results obtained from steady state neutronic calculations are shown in Table 7. shows good agreement with those showed in literature [8].…”

Section: Resultssupporting

confidence: 93%

Section: 1mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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One-step coupled calculations (Serpent-OpenFOAM) for a fuel rod of the IPR-R1 triga reactor

et al. 2021

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“…As simple as it is, FeenoX is still pretty flexible. A proof of this fact is that its applications range from coupling neutronics with CFD in nuclear reactors (Vasconcelos et al, 2018) to providing a back end to web-based thermo-mechanical solvers.…”

Section: Discussionmentioning

confidence: 99%