Uncertainty propagation based on correlated sampling technique for nuclear data applications

Laureau, Axel; Lamirand, Vincent; Rochman, D.; Pautz, Andreas

doi:10.1051/epjn/2020003

Cited by 5 publications

(3 citation statements)

References 17 publications

(21 reference statements)

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“…From these tools, a unique method was developed to optimize the experimental programme and to ensure feedback on nuclear data [49]. The stainless steel nuclear data uncertainties were propagated in a preliminary design of the experiments using a Monte Carlo methodology with the TENDL-2017 nuclear data library and correlated sampling for reducing the computational cost [50], [51]. The propagation resulted in expected reaction rates for a list of considered dosimetry reactions, with their corresponding distributions and covariance, for each measurement position in each metal reflector.…”

Section: ) Uncertainty Propagation and Experimental Designmentioning

confidence: 99%

Ten springs of experiments in CROCUS

Lamirand

2023

EPJ Web Conf.

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Around a decade ago, a new team rebuilt experimental research at EPFL’s nuclear facilities, and in particular in the CROCUS nuclear reactor. After a broad investigation and open discussions with colleagues from the nuclear community, a number of experiments and research directions were selected. They range from reactor physics to nuclear data, with a focus on instrumentation. We present here the variety of experiments carried out and how instrumentation has been instrumental in these perspectives. Developments on branching or intrinsic reactor noise were made possible thanks to extensive theoretical investigation coupled with the developments of pulse and current modes neutron detection systems, as well as the LEAF gamma detection array. With regard to modulation or perturbation reactor noise, a study of fuel rods vibration was carried out thanks to the unique COLIBRI in-core fuel rods oscillation device; in the VOID experiments, a method was tested to measure the void coefficient with neutron modulation; in the APRHODITE project, the PISTIL rotating absorber, or absorber of variable strength, was used to determine the zero power reactor transfer function, in order to obtain feedback on kinetics nuclear data, particularly delayed neutrons. On the topic of nuclear data, the PETALE programme consisted on criticality and transmission experiments for the study of stainless steel, using instrumented metal reflectors. New dosimetry methodologies were developed for consistent and complete propagation of uncertainties, which also enabled experiments to be optimized. It will be continued in the HARVEST-X project, and its pile-oscillation program, BLOOM. Last but not least, developments in dosimetry as well as for a novel miniature neutron scintillation technology (MiMi detectors) allowed for interand intrapin (NECTAR) neutron measurements. 160 MiMi detectors have recently been distributed throughout the CROCUS core in a unique 3D detector array called SAFFRON, paving the way for novel high-resolution neutronics.

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Section: ) Uncertainty Propagation and Experimental Designmentioning

confidence: 99%

Ten springs of experiments in CROCUS

Lamirand

2023

EPJ Web Conf.

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“…Hundreds of sampled cross sections are required for uncertainty propagation. For this reason an acceleration technique based on correlated sampling has been developed and is detailed in the twin article [5]. The principle of the correlated sampling is the modelling of a macroscopic cross section modification by a modification of the neutron weight in order to be representative of the analogue and the modified systems in a single neutron track.…”

Section: Total Monte Carlomentioning

confidence: 99%

“…These detectors consist of thin activation foils (<mm) of several materials in order to use different reactions to be sensitive to different parts of the neutron spectrum. Specific numerical developments have been required and are detailed in the twin article [5] to perform the propagation of nuclear data uncertainty on this kind of system.…”

Section: Introductionmentioning

confidence: 99%

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

Laureau

Lamirand

Rochman

et al. 2020

EPJ Nuclear Sci. Technol.

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The PETALE experimental programme in the CROCUS reactor intends to provide integral measurements to constrain stainless steel nuclear data. This article presents the tools and the methodology developed to design and optimize the experiments, and its operating principle. Two acceleration techniques have been implemented in the Serpent2 code to perform a Total Monte Carlo uncertainty propagation using variance reduction and correlated sampling technique. Their application to the estimation of the expected reaction rates in dosimeters is also discussed, together with the estimation of the impact of the nuisance parameters of aluminium used in the experiment structures. This is an Open Access article distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. ,

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Uncertainty propagation based on correlated sampling technique for nuclear data applications

Laureau

Lamirand

Rochman

et al. 2020

EPJ Nuclear Sci. Technol.

Self Cite

View full text Add to dashboard Cite

A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files. The TMC-CS (Total Monte Carlo with Correlated Sampling) approach offers an interesting speed-up of the associated computation time. This methodology is detailed in this paper, together with two application cases to validate and illustrate the gain provided by this technique: the highly enriched uranium/iron metal core reflected by a stainless-steel reflector HMI-001 benchmark, and the PETALE experimental programme in the CROCUS zero-power light water reactor.

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Uncertainty propagation based on correlated sampling technique for nuclear data applications

Cited by 5 publications

References 17 publications

Ten springs of experiments in CROCUS

Ten springs of experiments in CROCUS

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

Uncertainty propagation based on correlated sampling technique for nuclear data applications

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