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Quantification of the 35Cl($$\textit{n, p}$$) reaction channel

Journal Article · · Progress in Nuclear Energy
 [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
+ Show Author Affiliations

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

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1909132
Journal Information:
Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Vol. 157; ISSN 0149-1970
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (12)

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Determination of the 35Cl(n, p)35S reaction cross section and its astrophysical implications journal June 1994
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journal June 2015
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Figures / Tables (8)

FIG. 1(p. 2)figure FIG. 1
FIG. 2(p. 2)figure FIG. 2
FIG. 3(p. 3)figure FIG. 3
FIG. 4(p. 3)figure FIG. 4
FIG. 5(p. 4)figure FIG. 5
FIG. 6(p. 4)figure FIG. 6
FIG. 7(p. 4)figure FIG. 7
FIG. 8(p. 5)figure FIG. 8

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Hauser–Feshbach
Molten salt reactor
Nuclear Criticality Safety Program (NCSP)
Nuclear Data
Nuclear data evaluation
Nuclear data library
R-matrix