Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data

Dupré, Antoine; Vasiliev, A.; Ferroukhi, H.; Pautz, Andreas

doi:10.1016/j.anucene.2015.06.040

Cited by 11 publications

(7 citation statements)

References 4 publications

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“…It can be noted that typically the C/E-1 values observed from the relevant validation studies in the dosimetry domain fall within~±20% (see e.g., [62,67,68]) and this level of accuracy is considered normally as acceptable [1,60]. In more details, only a rather general and approximate assessment could be given here for demonstration purpose, based e.g., on the results published in [62,68]: for the 93 Nb fluence monitor the average (C/E-1) values obtained with the PWR-GP, PWR-ST and BWR-D validation models (with ENDF/B-VII.0 in [62] and ENDF/B-VII.1 in [68] as the base ND and CM library) were respectively~5%,~5% and~18%.…”

Section: General Description and Assessmentmentioning

confidence: 99%

“…In more details, only a rather general and approximate assessment could be given here for demonstration purpose, based e.g., on the results published in [62,68]: for the 93 Nb fluence monitor the average (C/E-1) values obtained with the PWR-GP, PWR-ST and BWR-D validation models (with ENDF/B-VII.0 in [62] and ENDF/B-VII.1 in [68] as the base ND and CM library) were respectively~5%,~5% and~18%. For the same models and the 54 Fe fluence monitors the (C/E-1) values were~−1%,~3% and~9%.…”

Section: General Description and Assessmentmentioning

confidence: 99%

“…Details of the experimental set up and a recent PSI analysis of the measured data, including obtained C/E results, can be found in [68]. Secondly, other experimental programs, called "scrapping tests" (ST), performed at the same PWR reactor are also considered.…”

Section: Description Of the Calculation Models And The Calculation Mementioning

confidence: 99%

“…Hereafter all considered sources of BWR experimental data for FNF modeling validation will be called "Dosimeters (D)". experiments can be found in [61,67,68]. Following the extraction of the irradiated samples from the reactor, specific activities of the material samples have been analyzed (partly at the PSI Hotlab) and later used for validation studies, in particular also performed at PSI [61,67].…”

Section: Description Of the Calculation Models And The Calculation Mementioning

confidence: 99%

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Exploring Stochastic Sampling in Nuclear Data Uncertainties Assessment for Reactor Physics Applications and Validation Studies

et al. 2016

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Abstract:The quantification of uncertainties of various calculation results, caused by the uncertainties associated with the input nuclear data, is a common task in nuclear reactor physics applications. Modern computation resources and improved knowledge on nuclear data allow nowadays to significantly advance the capabilities for practical investigations. Stochastic sampling is the method which has received recently a high momentum for its use and exploration in the domain of reactor design and safety analysis. An application of a stochastic sampling based tool towards nuclear reactor dosimetry studies is considered in the given paper with certain exemplary test evaluations. The stochastic sampling not only allows the input nuclear data uncertainties propagation through the calculations, but also an associated correlation analysis performance with no additional computation costs and for any parameters of interest can be done. Thus, an example of assessment of the Pearson correlation coefficients for several models, used in practical validation studies, is shown here. As a next step, the analysis of the obtained information is proposed for discussion, with focus on the systems similarities assessment. The benefits of the employed method and tools with respect to practical reactor dosimetry studies are consequently outlined.

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Section: General Description and Assessmentmentioning

confidence: 99%

Section: General Description and Assessmentmentioning

confidence: 99%

Section: Description Of the Calculation Models And The Calculation Mementioning

confidence: 99%

Section: Description Of the Calculation Models And The Calculation Mementioning

confidence: 99%

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Exploring Stochastic Sampling in Nuclear Data Uncertainties Assessment for Reactor Physics Applications and Validation Studies

et al. 2016

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“…The original purpose of the program is to measure the neutron transport through materials typical for "heavy reflectors" as found, for example, in the EPR reactor design and thus to provide validation data for the selected materials cross-sections and reflector properties. However, the PETALE setup can also be useful for providing experimental data applicable for validation of calculation methodologies for typical LWR reactor dosimetry applications, like the one being developed and validated at PSI [1], [2], [3]. Thus, a pertinent question which can * e-mail: alexander.vasiliev@psi.ch be posed is: how representative are the planned PETALE measurements for the validation of FNF predictions in LWR structures?…”

Section: Introductionmentioning

confidence: 99%

Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations

et al. 2020

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The international experimental program PETALE will be carried out at the CROCUS research reactor of EPFL. The program aims at measuring neutron penetration in slabs made of materials composing typical LWR reactor pressure vessel. The measurements will be used for code and nuclear data validation and for the evaluation of the reflecting properties of these materials. In this paper the representativity of the PETALE experiments is assessed with respect to operational LWR reactors dosimetry and activation evaluations using the Paul Scherrer Institute (PSI) in-house tool NUSS. The NUSS tool allows the stochastic sampling of nuclear data using covariance matrices available in modern nuclear data libraries and the subsequent running of a Monte Carlo code with the modified data files. The representativity can then be assessed based on the Pearson correlation coefficients. The ultimate goal of the work is first of all to assess if the planned PETALE measurements could be applicable beyond their primary purpose and serve for extending the PSI validation database for LWR reactor dosimetry evaluations. Secondly, provided that the PETALE measurements are found useful for the task above, the information on the correlations between the PETALE neutron detectors’ responses and the reactor dosimetry quantities of interest, shall be presented and discussed.

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