Abstract

Providing reliable estimates of the nuclear data contribution to the uncertainty of well-known integral benchmarks is fundamental to the validation and verification process for a nuclear data library. The Nuclear Energy Agency has produced and maintains the NDaST sensitivity tool, which integrates the DICE sensitivities and nuclear data covariances. This system has been used to rigorously and efficiently provide direct feedback to evaluators and streamline validation. For its future evolution and to identify high-priority development areas, NDaST is continuously compared against state-of-the-art codes that use different uncertainty propagation methodologies. In this work, NDaST was compared to the nuclear data sampling code SANDY for several ICSBEP criticality benchmarks using the JEFF-3.3 evaluated data. Despite excellent overall agreement for cross sections and fission neutron multiplcities, discrepancies due to processed covariance descriptions for angular distributions and prompt fission neutron spectra have identified areas where coordinated development of nuclear data covariance descriptions should be prioritised.

Highlights

  • The International Criticality Safety Benchmark Evaluation Project (ICSBEP) [1] provides a compilation of critical and subcritical benchmark experiment data that are maintained and continuously updated by the OECD/Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS)

  • The Joint Evaluated Fission and Fusion (JEFF)-3.3 nuclear data library was processed with NJOY and SANDY to produce a suite of derived files for nuclear data uncertainty propagation

  • Uncertainties and other moments were quantified for a selection of ICSBEP cases using the NEA sensitivity tool Nuclear Data Sensitivity Tool (NDaST) and the Monte Carlo sampling code SANDY in combination with MCNP

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Summary

Introduction

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) [1] provides a compilation of critical and subcritical benchmark experiment data that are maintained and continuously updated by the OECD/Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS). In parallel to the development of more complete nuclear data evaluations and covariances, computer codes have been developed to process and propagate these covariances to be able to quantify the uncertainty on various neutronics parameters, including keff. Semi-empirical model codes such as TALYS [11] are used to generate sampled nuclear data evaluations based on the direct sampling of parameters used within physics models. This has the added benefit of allowing complete freedom in the distributions of quantities in nuclear data that are often assumed to have Gaussian distributions. The study focused on newly implemented features using sensitivities to angular distributions and the propagation of these uncertainties

Uncertainty propagation tools
Uncertainty propagation with ICSBEP benchmarks
Jezebel
PU-MET-FAST
PU-MET-FAST-006
Propagation of covariances for Legendre polynomial coefficients
Conclusions
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