Benchmarking ENDF/B-VII.0

Marck, S. C. van der

doi:10.1016/j.nds.2006.11.002

Cited by 66 publications

(36 citation statements)

References 15 publications

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“…Similar approach has also been used in other ENDF/B-VII evaluations for important actinides, such as 235,238 U and 239 Pu [19]. Subsequent validation proved that the thus obtained improvements of inelastic scattering data largely improved library performance in integral benchmarking [20]. Our "deformed" MSD approach allows to achieve similar result on a physically sound basis.…”

Section: Resultsmentioning

confidence: 72%

Deformation dependent TUL multi-step direct model

Wienke

Capote

Herman

et al. 2007

Nd2007

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Abstract. The Multi-Step Direct (MSD) module TRISTAN in the nuclear reaction code EMPIRE has been extended to account for nuclear deformation. The new formalism was tested in calculations of neutron emission spectra emitted from the 232 Th(n,xn) reaction. These calculations include vibration-rotational Coupled Channels (CC) for the inelastic scattering to low-lying collective levels, "deformed" MSD with quadrupole deformation for inelastic scattering to the continuum, Multi-Step Compound (MSC) and Hauser-Feshbach with advanced treatment of the fission channel. Prompt fission neutrons were also calculated. The comparison with experimental data shows clear improvement over the "spherical" MSD calculations and JEFF-3.1 and JENDL-3.3 evaluations.

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Section: Resultsmentioning

confidence: 72%

Deformation dependent TUL multi-step direct model

Wienke

Capote

Herman

et al. 2007

Nd2007

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“…These benchmarks were already extensively studied for the validation of the ENDF/B-VII.0 library in Ref. [10]. For each of the selected benchmarks, the impact of the nuclear data uncertainty for a single isotope is studied.…”

Section: Methodsmentioning

confidence: 99%

Propagation of nuclear data uncertainty: Exact or with covariances

Rochman

Koning

Marck

et al. 2010

EPJ Web of Conferences

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Abstract. Two distinct methods of propagation for basic nuclear data uncertainties to large scale systems will be presented and compared. The "Total Monte Carlo" method is using a statistical ensemble of nuclear data libraries randomly generated by means of a Monte Carlo approach with the TALYS system. These libraries are then directly used in a large number of reactor calculations (for instance with MCNP) after which the exact probability distribution for the reactor parameter is obtained. The second method makes use of available covariance files and can be done in a single reactor calculation (by using the perturbation method). In this exercise, both methods are using consistent sets of data files, which implies that covariance files used in the second method are directly obtained from the randomly generated nuclear data libraries from the first method. This is a unique and straightforward comparison allowing to directly apprehend advantages and drawbacks of each method. Comparisons for different reactions and criticality-safety benchmarks from 19 F to actinides will be presented. We can thus conclude whether current methods for using covariance data are good enough or not.

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“…Systematic discrepancies are observed in criticality safety benchmarks containing tungsten [2], fusion neutronics benchmarks [3], and measured constants for neutron activation [4]. These discrepancies motivated the work presented herein.…”

Section: Introductionmentioning

confidence: 90%

Evaluation of tungsten isotopes in the fast neutron range including cross section covariance estimation

Capote

Trkov

Kodeli³

et al. 2007

Nd2007

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Abstract. New evaluations for the tungsten isotopes 180,182,183,184,186 W in the neutron energy range up to 60 MeV were produced. In the resonance range only minor adjustments to the resonance parameters were made due to a lack of adequate experimental data. Evaluations in the fast energy region were based on nuclear model calculations using the EMPIRE-2.19 code. Recently derived dispersive coupled-channel optical model potentials for W and Ta isotopes were instrumental to achieve a very good description of the available microscopic cross section database. Model covariance data were generated with the Monte Carlo technique to produce a prior estimate for the covariance matrix. Experimental data were introduced through the GANDR system. The evaluated files were tested on selected fusion neutronics benchmarks and showed marked improvement compared to other existing evaluations.

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Benchmarking ENDF/B-VII.0

Cited by 66 publications

References 15 publications

Deformation dependent TUL multi-step direct model

Deformation dependent TUL multi-step direct model

Propagation of nuclear data uncertainty: Exact or with covariances

Evaluation of tungsten isotopes in the fast neutron range including cross section covariance estimation

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