Benchmarking ENDF/B-VII.1, JENDL-4.0 and JEFF-3.1.1 with MCNP6

Marck, S. C. van der

doi:10.1016/j.nds.2012.11.003

Cited by 54 publications

(18 citation statements)

References 27 publications

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“…Finally, concerning the overall behavior of the ENDF/ B-VII.1, JENDL-4.0, and JEFF-3.1.1 evaluations for gadolinium isotopes, it is important to quote the gigantic work performed by van der Marck [25] published in 2012. In this work, more than 2000 benchmarks from the ICSBEP database were calculated with MCNP6 using the abovementioned evaluated libraries.…”

Section: Referencementioning

confidence: 99%

Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations

Rocchi

Guglielmelli

Castelluccio

et al. 2017

EPJ Nuclear Sci. Technol.

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Gadolinium odd isotopes cross sections are crucial in assessing the neutronic performance and safety features of a light water reactor (LWR) core. Accurate evaluations of the neutron capture behavior of gadolinium burnable poisons are necessary for a precise estimation of the economic gain due to the extension of fuel life, the residual reactivity penalty at the end of life, and the reactivity peak for partially spent fuel for the criticality safety analysis of Spent Fuel Pools. Nevertheless, present gadolinium odd isotopes neutron cross sections are somehow dated and poorly investigated in the high sensitivity thermal energy region and are available with an uncertainty which is too high in comparison to the present day typical industrial standards and needs. This article shows how the most recent gadolinium cross sections evaluations appear inadequate to provide accurate criticality calculations for a system with gadolinium fuel pins. In this article, a sensitivity and uncertainty analysis (S/U) has been performed to investigate the effect of gadolinium odd isotopes nuclear cross sections data on the multiplication factor of some LWR fuel assemblies. The results have shown the importance of gadolinium odd isotopes in the criticality evaluation, and they confirmed the need of a re-evaluation of the neutron capture cross sections by means of new experimental measurements to be carried out at the n_TOF facility at CERN.

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Section: Referencementioning

confidence: 99%

Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations

Rocchi

Guglielmelli

Castelluccio

et al. 2017

EPJ Nuclear Sci. Technol.

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show abstract

“…Furthermore, from a regulatory perspective it is probably the least attractive as the results depend on the number of benchmarks, i.e., traditional validation is strongly user-dependent. For example, let consider calculated using two versions of JEFF library (3.1.1 and 3.3t2) [10] of ICSBEP [2] benchmarks.…”

Section: Phenomenological Validation Strategiesmentioning

confidence: 99%

Methodology and issues of integral experiments selection for nuclear data validation

2017

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Abstract. Nuclear data validation involves a large suite of Integral Experiments (IEs) for criticality, reactor physics and dosimetry applications.[1] Often benchmarks are taken from international Handbooks. [2,3] Depending on the application, IEs have different degrees of usefulness in validation, and usually the use of a single benchmark is not advised; indeed, it may lead to erroneous interpretation and results. [1] This work aims at quantifying the importance of benchmarks used in application dependent cross section validation. The approach is based on well-known General Linear Least Squared Method (GLLSM) extended to establish biases and uncertainties for given cross sections (within a given energy interval). The statistical treatment results in a vector of weighting factors for the integral benchmarks. These factors characterize the value added by a benchmark for nuclear data validation for the given application. The methodology is illustrated by one example, selecting benchmarks for 239 Pu cross section validation.

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“…Calculation values of k eff except for three data of HMF-064 are taken from the results obtained by Okumura and Nagaya with MVP-II [4], and those of the HMF-064 data are taken from the results obtained by van der Marck with MCNP [5]. Statistical uncertainties of these results are negligibly small, so uncertainties of 0.001% are assumed to all these calculation values.…”

Section: Calculation Values With Their Uncertaintiesmentioning

confidence: 99%

On prediction accuracy of neutronics parameters of accelerator-driven system

et al. 2017

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Abstract. Nuclear data-induced uncertainty of neutronics parameters of one specific ADS design is quantified. The nuclear data adjustment method with available integral data is employed to reduce the uncertainties, and usefulness of these integral data is investigated. Numerical results reveal that the uncertainty reduction by the present nuclear data adjustment is insignificant and restrictive. Future perspecitives are also provided.

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Benchmarking ENDF/B-VII.1, JENDL-4.0 and JEFF-3.1.1 with MCNP6

Cited by 54 publications

References 27 publications

Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations

Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations

Methodology and issues of integral experiments selection for nuclear data validation

On prediction accuracy of neutronics parameters of accelerator-driven system

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