EPJ Web Conf.
Volume 261, 2022Applied Nuclear Physics Conference (ANPC 2021)
|Number of page(s)||6|
|Section||Ion and Neutron Beam Irradiation of Materials|
|Published online||11 April 2022|
Effect of Using Different Data Libraries and Simulation Codes on the Calculation of Spectra and Operational Quantities for the D2O-252Cf Source at PTB
Physikalisch-Technische Bundesanstalt (PTB), Bundesallee 100, 38116 Braunschweig, Germany
* Corresponding author: firstname.lastname@example.org
Published online: 11 April 2022
The neutron reference field produced by a heavy-water moderated 252Cf source is used at PTB for calibrating neutron-measuring devices. Knowledge of the precise neutron spectrum is very important for the investigation of operational radiation protection quantities. Recently, new fission spectrum data of 252Cf has been proposed based on the latest nuclear data library version. At PTB, earlier calculations for the D2O moderated 252Cf neutron source were carried out more than 20 years ago, thus updated and more detailed calculations are required. In this paper, a detailed simulation model of the PTB moderated 252Cf source assembly has been prepared and investigated using new spectral data and two different Monte Carlo transport codes MCNP6.1 and PHITS3.22, with ENDF/BVIII.0, ENDF/B-VII.1, ENDF/B-V, and ENDL85 evaluated nuclear data libraries. The results show that the evaluated nuclear data libraries influence the calculated operational quantities by (3-5) %. The dosimetric quantities calculated with the PHITS code and the ENDF/B-VII.1 data library agree well with the MCNP6 results.
© The Authors, published by EDP Sciences, 2022
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