Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor

Siefman, Daniel; Girardin, G.; Rais, Adolfo; Pautz, Andreas; Hursin, Mathieu

doi:10.1016/j.anucene.2015.05.004

Cited by 18 publications

(3 citation statements)

References 5 publications

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“…The experimental design consists of selecting dosimeters, reactor power and operation time. It was accomplished with simulated activation experiments using the Monte Carlo neutron transport code Serpent2 [8], under criticality configuration based on the modeling in [9].…”

Section: B Experimental Designmentioning

confidence: 99%

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

et al. 2020

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The present article describes the preliminary validation study of simulated in-core and reflector n eutron spectra in preparation of oncoming experimental programs in the zeropower reactor CROCUS at EPFL. For this purpose, a set of activation foils were irradiated at three characteristic positions in the CROCUS reactor, and the subsequent activities were analyzed via γ spectrometry. The experimental setup was then modeled with the Monte Carlo neutron transport code Serpent2 and associated with an analysis tool to include the effect of the reactor power history during experiments. The comparison of calculated and measured reaction rates (C/E) indicates a general consistency (at 2σ) between calculated and measured spectra. However, offsets of C/E values were observed in (n, γ) reactions, up to 18% for 115In and 8% for 63Cu dosimeters. This could be caused by an unexpected isotopic composition, uncertainties in nuclear data, or the spectrometry analysis. In addition, a 100-groups spectrum unfolding was performed using the experimentally determined reaction rates and the Serpent2 spectra as the prior knowledge. The unfolded spectra were mainly adjusted in the thermal and fast ranges, while few modifications w ere m ade i n t he e pithermal r egion d ue t o the low contribution of epithermal neutrons in activation processes. Moreover, within energy groups where the capture reactions show resonant behavior, flux depletion (up to 38% as compared to the prior spectra) is observed due to the absence of self-shielding effect in the unfolding process. For this purpose, an unfolding method based on energy groups weighting is developed and tested.

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Section: B Experimental Designmentioning

confidence: 99%

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

et al. 2020

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“…CROCUS is an experimental zero-power reactor, uranium-fuelled and water-moderated, dedicated to education in radiation and reactor physics, and to research [6][7][8][9][10][11][12][13][14][15][16][17]. A complete description of the core can be found in the International Reactor Physics Experiments Handbook (IRPhE) [18].…”

Section: The Crocus Reactormentioning

confidence: 99%

An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor

Lamirand

Laureau

Rochman³

et al. 2019

EPJ Web Conf.

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The PETALE experimental programme in the CROCUS reactor at EPFL intends to contribute to the validation and improvement of neutron nuclear data in the MeV energy range for stainless steel, particularly in the prospect of heavy reflector elements of pressurized water reactors. It mainly consists of several transmission experiments: first, through metallic sheets of nuclear-grade stainless steel interleaved with dosimeter foils, and, successively, through its elemental components of interest – iron, nickel, and chromium. The present article describes the study for optimizing the response of the dosimetry experiments to the nuclear data of interest.

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“…In a previous work [12] the cross-section generation of the CROCUS reactor core was performed using Serpent code version 1.1.19. The SerpentXS python script [13] was used along with Serpent 1.1.19 to perform branch calculations and print cross sections into a PARCS compatible format.…”

Section: Cross-section Generationmentioning

confidence: 99%

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

Rais

Siefman

Girardin

et al. 2015

Science and Technology of Nuclear Installations

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In order to analyze the steady state and transient behavior of the CROCUS reactor, several methods and models need to be developed in the areas of reactor physics, thermal-hydraulics, and multiphysics coupling. The long-term objectives of this project are to work towards the development of a modern method for the safety analysis of research reactors and to update the Final Safety Analysis Report of the CROCUS reactor. A first part of the paper deals with generation of a core simulator nuclear data library for the CROCUS reactor using the Serpent 2 Monte Carlo code and also with reactor core modeling using the PARCS code. PARCS eigenvalue, radial power distribution, and control rod reactivity worth results were benchmarked against Serpent 2 full-core model results. Using the Serpent 2 model as reference, PARCS eigenvalue predictions were within 240 pcm, radial power was within 3% in the central region of the core, and control rod reactivity worth was within 2%. A second part reviews the current methodology used for the safety analysis of the CROCUS reactor and presents the envisioned approach for the multiphysics modeling of the reactor.

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Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor

Cited by 18 publications

References 5 publications

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

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