Document Type

Article

Publication Date

1-1-2017

Abstract

The neutron-capture reaction is fundamental for identifying and analyzing the γ-ray spectrum from an unknown assembly because it provides unambiguous information on the neutron-absorbing isotopes. Nondestructive-assay applications may exploit this phenomenon passively, for example, in the presence of spontaneous-fission neutrons, or actively where an external neutron source is used as a probe. There are known gaps in the Evaluated Nuclear Data File libraries corresponding to neutron-capture γ-ray data that otherwise limit transport-modeling applications. In this work, we describe how new thermal neutron-capture data are being used to improve information in the neutron-data libraries for isotopes relevant to nonproliferation applications. We address this problem by providing new experimentally-deduced partial and total neutron-capture reaction cross sections and then evaluate these data by comparison with statistical-model calculations.

Comments

This is an Open Access article, distributed under the terms of the Creative Commons Attribution licence (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted re-use, distribution, and reproduction in any medium, provided the original work is properly cited. CC BY 4.0.
Sourced from the publisher version of record at EPJWeb: https://doi.org/10.1051/epjconf/201714609008

Article derived from a paper presented at ND 2016: International Conference on Nuclear Data for Science and Technology

DOI

10.1051/epjconf/201714609008

Source Publication

EPJ Web of Conferences

Included in

Nuclear Commons

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