Authors & Affiliations

Rozikhin E.V., Yakunin A.A., Koscheev V.N., Peregudov A.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Rozikhin E.V. – Senior Research, A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7(484) 399-51-54; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Yakunin A.A. – Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
Koscheev V.N. – Leading Research, Cand. Sci. (Phis.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering.
Peregudov A.A. – Senior Research, Cand. Sci. (Tech.), A.I. Leypunsky Institute for Physics and Power Engineering.

Abstract

Cross verification of software tools is one of the main methods for calculational uncertainty assessment of physical functionals in the field of calculations of neutron-physical parameters of reactor facilities. For example, in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook), the authors of the evaluation usually provide the results of benchmark model calculations for various systems of constants and calculational codes.
For software users, the MCNP code, which utilize continuous-energy cross sections, is the benchmark for obtaining reliable calculation results. Therefore the MCNP code is usually used for verification of the developing evaluated nuclear data libraries. Traditionally, nuclear data for MCNP in the ACE format are prepared using the processing code NJOY. Recently, other programs have appeared that have the option of providing nuclear data in the ACE format.
Recently in this field of activity the "old/new" SCALE code system, intended for criticality safety licensing of nuclear facilities, was appeared. "Old", because there is an extensive experience with the use of various group libraries of nuclear data. "New", because in the latest version of the complex it is possible to calculate physical characteristics using continuous energy cross sections. The nuclear data for the SCALE6 code system is prepared with the AMPX-6 processing code, whose capabilities are significantly extended in comparison with the previous version. The format of representation of continuous energy nuclear data is the original development of AMPX-6 and does not coincide with the widely known ACE format.
Results of usage of the SCALE6.2 code system are presented below. Experience on development of nuclear data libraries based on the ENDF/B-VII.1 and ROSFOND-2010 libraries is outlined.
Results of cross-verification of the code systems MCNP5 and SCALE 6.2 on a specialized set of benchmarks from the ICSBEP international handbook are presented. The peculiarity of the selected models is that they have been used for many years to verify the ABBN constant system, first as models from the ENDF202 collection, and then from the ICSBEP international handbook. All the models are characteristic for reactor assemblies with a fast and intermediate neutron spectrum.

Keywords
cross-verification of software tools, MCNP code, SCALE code system, NJOY processing code, AMPX processing code, ENDF/B-VII.1 nuclear data library, ROSFOND-2010 nuclear data library, International Handbook of Evaluated Criticality Safety Benchmark Experiments

Article Text (PDF, in Russian)

References

UDC 004.94:681.3.06

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2018, issue 2, 2:12