TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code

Brun, Emeric; Damian, F.; Diop, Cheikh M’Backé; Dumonteil, Éric; Hugot, F. X.; Jouanne, C.; Lee, Y.K.; Malvagi, Fausto; Mazzolo, Alain; Petit, Odile; Trama, Jean-Christophe; Visonneau, Thierry; Zoia, Andrea

doi:10.1016/j.anucene.2014.07.053

Cited by 303 publications

(139 citation statements)

References 22 publications

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“…The importance map generator INIPOND module of TRIPOLI-4 can also be used to improve the variance reduction performance and to reduce the user involvement, especially for the neutron deep penetration cases [3][4][5][6][7][8]. The generated important map is then used by TRIPOLI-4 in the same run to perform importance sampling through the exponential transform method, quota sampling, splitting and Russian roulette, and source biasing.…”

Section: Tripoli-4 Variance Reduction Techniquesmentioning

confidence: 99%

“…For the neutron activation calculation of shielding and structure materials of nuclear facilities, the knowledge of 3D neutron flux map and the energy spectra must be first investigated. In this kind of neutron deep penetration calculation in shielding, variance reduction techniques are necessary in order to reduce the uncertainty of the Monte-Carlo calculations [3,4]. Different water shielding benchmarks are available from the OECD/NEA SINBAD database.…”

Section: Introductionmentioning

confidence: 99%

“…The continuous-energy Monte-Carlo radiation transport code TRIPOLI-4 has been used for radiation protection and shielding analyses [3]. To develop its application on nuclear decommissioning activities, both experimental and computational benchmarks are being developed and performed.…”

Section: Introductionmentioning

confidence: 99%

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Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

Lee

2017

EPJ Web Conf.

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Nuclear decommissioning takes place in several stages due to the radioactivity in the reactor structure materials. A good estimation of the neutron activation products distributed in the reactor structure materials impacts obviously on the decommissioning planning and the low-level radioactive waste management. Continuous energy Monte-Carlo radiation transport code TRIPOLI-4 has been applied on radiation protection and shielding analyses. To enhance the TRIPOLI-4 application in nuclear decommissioning activities, both experimental and computational benchmarks are being performed. To calculate the neutron activation of the shielding and structure materials of nuclear facilities, the knowledge of 3D neutron flux map and energy spectra must be first investigated. To perform this type of neutron deep penetration calculations with the Monte Carlo transport code, variance reduction techniques are necessary in order to reduce the uncertainty of the neutron activation estimation. In this study, variance reduction options of the TRIPOLI-4 code were used on the NAIADE 1 light water shielding benchmark. This benchmark document is available from the OECD/NEA SINBAD shielding benchmark database. From this benchmark database, a simplified NAIADE 1 water shielding model was first proposed in this work in order to make the code validation easier. Determination of the fission neutron transport was performed in light water for penetration up to 50 cm for fast neutrons and up to about 180 cm for thermal neutrons. Measurement and calculation results were benchmarked. Variance reduction options and their performance were discussed and compared.

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Section: Tripoli-4 Variance Reduction Techniquesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

Lee

2017

EPJ Web Conf.

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“…• The numerical validation consists in comparing the results given by the package against the results given by a reference calculation, here it is with TRIPOLI4 [10]. This allows a quantification of the biases induced by the modelling approximations in the resolution method of the calculation scheme tested.…”

Section: The Vvuq Processmentioning

confidence: 99%

Work plan for improving the DARWIN2.3 depleted material balance calculation of nuclides of interest for the fuel cycle

et al. 2017

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Abstract. DARWIN2.3 is the reference package used for fuel cycle applications in France. It solves the Boltzmann and Bateman equations in a coupling way, with the European JEFF-3.1.1 nuclear data library, to compute the fuel cycle values of interest. It includes both deterministic transport codes APOLLO2 (for light water reactors) and ERANOS2 (for fast reactors), and the DARWIN/PEPIN2 depletion code, each of them being developed by CEA/DEN with the support of its industrial partners.The DARWIN2.3 package has been experimentally validated for pressurized and boiling water reactors, as well as for sodium fast reactors; this experimental validation relies on the analysis of post-irradiation experiments (PIE).The DARWIN2.3 experimental validation work points out some isotopes for which the depleted concentration calculation can be improved. Some other nuclides have no available experimental validation, and their concentration calculation uncertainty is provided by the propagation of a priori nuclear data uncertainties.This paper describes the work plan of studies initiated this year to improve the accuracy of the DARWIN2.3 depleted material balance calculation concerning some nuclides of interest for the fuel cycle.

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“…NARMER-1 is part of a set of software developed by SERMA in the broad field of reactor studies. It is closely related to TRIPOLI-4 ® [7] as it uses the same geometry package allowing easier comparison to this reference Monte Carlo code for validation purpose. Depending on the period, up to 5 people have been contributing to MERCURE and now to NARMER-1, their activities covering development, integration & architecture, V&V, documentation, user support, distribution and licensing.…”

Section: Introductionmentioning

confidence: 99%

NARMER-1: a photon point-kernel code with build-up factors

et al. 2017

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Abstract. This paper presents an overview of NARMER-1, the new generation of photon point-kernel code developed by the Reactor Studies and Applied Mathematics Unit (SERMA) at CEA Saclay Center. After a short introduction giving some history points and the current context of development of the code, the paper exposes the principles implemented in the calculation, the physical quantities computed and surveys the generic features: programming language, computer platforms, geometry package, sources description, etc. Moreover, specific and recent features are also detailed: exclusion sphere, tetrahedral meshes, parallel operations. Then some points about verification and validation are presented. Finally we present some tools that can help the user for operations like visualization and pre-treatment.

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TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code

Cited by 303 publications

References 22 publications

Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

Work plan for improving the DARWIN2.3 depleted material balance calculation of nuclides of interest for the fuel cycle

NARMER-1: a photon point-kernel code with build-up factors

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