Reproducibility of (n,γ) gamma ray spectrum in Pb under different ENDF/B releases

Radiative capture reactions are of interest in shielding design and other fundamental research. In this study the reproducibility of (n,γ) reactions in Pb when cross-section data from different ENDF/B releases are used in the Monte-Carlo code, MCNP, was investigated. Pb was selected for this study b...

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Bibliographic Details
Published in:	Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms Vol. 373; pp. 1 - 4
Main Authors:	Kebwaro, J.M., He, C.H., Zhao, Y.L.
Format:	Journal Article
Language:	English
Published:	Elsevier B.V 15-04-2016
Subjects:	Beam interactions Computer simulation ENDF/B cross-section data releases Format Gamma rays Monte Carlo methods Radiative capture Reactions (nuclear) Reproducibility Shielding Pb Radiative capture ENDF/B cross-section data releases Reproducibility
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Summary:	Radiative capture reactions are of interest in shielding design and other fundamental research. In this study the reproducibility of (n,γ) reactions in Pb when cross-section data from different ENDF/B releases are used in the Monte-Carlo code, MCNP, was investigated. Pb was selected for this study because it is widely used in shielding applications where capture reactions are likely to occur. Four different neutron spectra were declared as source in the MCNP model which consisted of a simple spherical geometry. The gamma ray spectra due to the capture reactions were recorded at 10cm from the center of the sphere. The results reveal that the gamma ray spectrum produced by ENDF/B-V is in reasonable agreement with that produced when ENDF/B-VI.6 is used. However the spectrum produced by ENDF/B-VII does not reveal any primary gamma rays in the higher energy region (E>3MeV). It is further observed that the intensities of the capture gamma rays produced when various releases are used differ by a some margin showing that the results are not reproducible. The generated spectra also vary with the spectrum of the source neutrons. The discrepancies observed among various ENDF/B releases could raise concerns to end users and need to be addressed properly during benchmarking calculations before the next release. The evaluation from ENDF to ACE format that is supplied with MCNP should also be examined because errors might have arisen during the evaluation.
Bibliography:	ObjectType-Article-1 SourceType-Scholarly Journals-1 ObjectType-Feature-2 content type line 23
ISSN:	0168-583X 1872-9584
DOI:	10.1016/j.nimb.2016.02.028