Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

DOI: 10.55176/2414-1038-2020-3-72-79

Authors & Affiliations

Zherdev G.M., Suvorov A.P.

A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Zherdev G.M. – Leading Researcher, Cand. Sci. (Phys.-Math.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7(484) 399-82-65; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Suvorov A.P. – Senior Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.


The computer program is intended for design and operational calculations that serve to substantiate the safety of nuclear facilities in documents submitted to ROSTEKHNADZOR and declared as a means of engineering calculations of radiation characteristics of spent fuel assemblies declared in the following topics: calculation of radiation protection and radiation safety of nuclear facilities; neutron-physical calculations (nuclide composition calculations). The computer program can be used independently or as part of other software systems for calculating the characteristics of objects consisting of spent fuel assemblies of uranium-graphite reactors EGP-6, AMB and AM and / or their parts. Computer program Nuclear Calculator EGP-6 2.0 is a set of WIMS-D5B and ORIGEN-S programs, as well as a number of auxiliary programs that provide both the preparation of initial data for the above programs and their interaction, and the processing of results to obtain radiation characteristics. The program has been thoroughly verified and validated. Today the program is a working tool for engineering and operational calculations, focused on the end user. Uses simple and straightforward inputs. The results are prepared in the format required by the customer. The state registration of the program was carried out.

computer program, activity, nuclide composition, radiation safety, energy release, EGP-6, spent fuel assemblies, one-group constants, isotope kinetics calculation, neutron sources, uranium-graphite reactor

Article Text (PDF, in Russian)


UDC 621.039.31.17

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2020, issue 3, 3:8