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Start Over Author "Heyse, J." Journal annals of nuclear energy
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3. Review of the natC(n,γ) cross section and criticality calculations of the graphite moderated reactor BR1.

Author

Díez, C.J., Stankovskiy, A., Malambu, E., Žerovnik, G., Schillebeeckx, P., Van den Eynde, G., Heyse, J., and Cabellos, O.

Subjects
*NUCLEAR cross sections, *CRITICALITY (Nuclear engineering), *GRAPHITE, *ORGANIC moderated reactors, *NUCLEAR physics experiments, *COMPARATIVE studies, *THERMAL analysis, *DATA analysis
Abstract

Highlights: [•] Review of the experimental and evaluated data for natC(n,γ) and 12C(n,γ). [•] Comparison of ENDF/B-VII.1 and JEFF-3.1.2 within BR1 criticality calculations. [•] The thermal capture cross section is of importance in large graphite-systems like BR1. [•] The 12C(n th ,γ) given by Firestone and Révay (2011) is recommended to be used. [•] The JENDL-4.0 evaluation takes the latest experimental data available. [ABSTRACT FROM AUTHOR]

Published
2013
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