RTS&T Monte Carlo code (facilities and computation methods)

Author

Blokhin, A.I. ; Degtyarev, I.I. ; Lokhovitskii, A.E. ; Maslov, M.A. ; Yazynin, I.A.

Author_Institution

Inst. of Phys. & Power Eng., Obninsk, Russia

Volume

1

fYear

1997

fDate

12-16 May 1997

Firstpage

258

Abstract

The paper describes facilities and computation methods of the new RTS&T Monte Carlo code. This code performs simulations of three dimensional electromagnetic shower development and low energy neutron production and transport in accelerator and in shielding components with a calculation of the isotope transmutation problem. RTS&T is based on a compilation from ENDF/B-VI, JENDL-3, EAF, FENDL and EPNDL evaluated data libraries to detailed physical process simulation and only a few approximations are made. It is possible to use RTS&T to solve the critical reactor problem. A combinatorial method of geometry definition is provided with the program. Recently the RTS& T code interface to the ANSYS 4.4 code system has been developed and tested

Keywords

Monte Carlo methods; combinatorial mathematics; neutron transport theory; shielding; ANSYS 4.4 code; EAF; ENDF/B-VI; EPNDL; FENDL; JENDL-3; Monte Carlo code; RTS&T code; critical reactor; isotope transmutation; low energy neutron production; neutron transport; shielding components; three dimensional electromagnetic showers; Computational modeling; Electromagnetic shielding; Geometry; Inductors; Isotopes; Libraries; Monte Carlo methods; Neutrons; Production; System testing;

fLanguage

English

Publisher

ieee

Conference_Titel

Particle Accelerator Conference, 1997. Proceedings of the 1997

Conference_Location

Vancouver, BC

Print_ISBN

0-7803-4376-X

Type

conf

DOI

10.1109/PAC.1997.749611

Filename

749611