Quantification of the 35Cl(n,p) reaction channel

M. T. Pigni

doi:10.1016/j.pnucene.2022.104551

Quantification of the ³⁵Cl(n,p) reaction channel

M. T. Pigni

Nuclear Data

Research output: Contribution to journal › Article › peer-review

1 Scopus citations

Abstract

The evaluated ³⁵Cl(n,p) cross sections in the ENDF/B-VIII.0 nuclear data library remain uncertain because of the lack of measured data in the 100–600 keV neutron energy range. In this energy region, the R-matrix analysis relies heavily on estimated (n,p) partial widths and level density information. This resulted in significant differences for the evaluated cross sections and predicted reactivity in nuclear reactor applications with respect to previous nuclear data libraries. This paper presents a methodology to quantify the cross sections for the ³⁵Cl(n,p) reaction channel from the combination of measured total cross sections and model calculations.

Original language	English
Article number	104551
Journal	Progress in Nuclear Energy
Volume	157
DOIs	https://doi.org/10.1016/j.pnucene.2022.104551
State	Published - Mar 2023

Funding

This work was supported by the US Department of Energy (DOE), Nuclear Criticality Safety Program (NCSP) funded and managed by the National Nuclear Security Administration (NNSA) for DOE, United States of America. The author thanks Sean Kuvin of Los Alamos National Laboratory and Lee Bernstein of Lawrence Berkeley National Laboratory for insightful discussions on the experimental techniques used in the (n,p) measurements. This work was supported by the US Department of Energy (DOE) , Nuclear Criticality Safety Program (NCSP) funded and managed by the National Nuclear Security Administration (NNSA) for DOE, United States of America .

Keywords

Hauser–Feshbach
Molten salt reactor
Nuclear data evaluation
Nuclear data library
R-matrix

Access to Document

10.1016/j.pnucene.2022.104551

Cite this

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abstract = "The evaluated 35Cl(n,p) cross sections in the ENDF/B-VIII.0 nuclear data library remain uncertain because of the lack of measured data in the 100–600 keV neutron energy range. In this energy region, the R-matrix analysis relies heavily on estimated (n,p) partial widths and level density information. This resulted in significant differences for the evaluated cross sections and predicted reactivity in nuclear reactor applications with respect to previous nuclear data libraries. This paper presents a methodology to quantify the cross sections for the 35Cl(n,p) reaction channel from the combination of measured total cross sections and model calculations.",

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