Published September 2014 | Version v1
Journal article

Improvement on the calculation of D2O moderated critical systems with new thermal neutron scattering libraries

  • 1. Neutron Physics Department and Instituto Balseiro, Centro Atómico Bariloche (Argentina)
  • 2. Atomic Energy of Canada Ltd., Chalk River Laboratories, Chalk River, ON K0J 1J0 (Canada)

Description

Highlights: • We analize the performance of neutron scattering libraries for D and O in D2O for nuclear criticality calculations. • We calculated 65 ICSBEP benchmark cases from 8 heavy water moderated thermal systems using MCNP5. • A significant improvement is found when our library is combined with the ROSFOND-2010 evaluation for deuterium. • In 48 of the 65 benchmark cases we obtained a C/E ratio closer to 1.0. • The percentage of benchmark cases calculated within 1-sigma increases from 42% to 82%, compared to ENDF/B-VII calculations. - Abstract: To improve the evaluations in thermal sublibraries, we developed a set of thermal neutron scattering cross sections (scattering kernels) for the deuterium and oxygen bound in heavy water in the ENDF-6 format. These new libraries are based on molecular dynamics simulations and recent experimental data, and result in an improvement of the calculation of single neutron scattering quantities. In this work, we show how the use of this new set of cross sections also improves the calculation of thermal critical systems moderated and/or reflected with heavy water. The use of the new thermal scattering library for heavy water, combined with the ROSFOND-2010 evaluation of the deuterium cross sections, results in an improvement of the C/E ratio in 48 out of 65 benchmark cases calculated with the Monte Carlo code MCNP5, in comparison with the existing library based on the ENDF/B-VII evaluation

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2014.03.024

Additional details

Identifiers

DOI
10.1016/j.anucene.2014.03.024;
PII
S0306-4549(14)00146-7;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
71
Journal Page Range
p. 206-210
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.