A Nuclear Data Evaluation Pipeline for the Fast Neutron Energy Range – using heteroscedastic Gaussian processes to treat model defects

In this paper, we discuss the development of a nuclear data evaluation pipeline, based around the TALYS code system. The pipeline focuses on the evaluation of the fast neutron energy range, above the resolved resonances. A strong focus in development lies on automation and reproducibility, as well a...

Full description

Saved in:
Bibliographic Details
Published inEPJ Web of Conferences Vol. 294; p. 4005
Main Authors Göök, Alf, Andersson-Sundén, Erik, Hansson, Joachim, Sjöstrand, Henrik
Format Journal Article Conference Proceeding
LanguageEnglish
Published Les Ulis EDP Sciences 2024
Subjects
Algorithms
Cross-sections
Defects
Fast neutrons
Gaussian process
Online AccessGet full text

Cover

More Information
Summary:In this paper, we discuss the development of a nuclear data evaluation pipeline, based around the TALYS code system. The pipeline focuses on the evaluation of the fast neutron energy range, above the resolved resonances. A strong focus in development lies on automation and reproducibility, as well as the efficient use of large-scale computational infrastructure, to enable rapid testing of new algorithms and modified assumptions. Several novel concepts for nuclear data evaluation methodology are implemented. A particular problem in evaluating the neutron-induced reaction cross-section using TALYS, relates to the intermediate energy range. While TALYS only predicts the smooth energy-averaged cross-section, experiments reveal unresolved resonance-like structures. In this paper, we explore ways to treat this type of model defect using heteroscedastic Gaussian processes to automatically determine the distribution of experimental data around an energy-averaged cross-section curve.
ISSN:2100-014X
2101-6275
2100-014X
DOI:10.1051/epjconf/202429404005