PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Данилычев А.В., Елистратов Д.Г., Стогов В.Ю.
State Scientific Centre - A.I. Leipunsky Institute for Physics and Power Engineering, Obninsk, Russia

Abstract

The admissibility of calculational deviations in value of reactivity coefficients obtained by various calculation methods for test model of IAEA (the reactor AI-600 with a hybrid core) is analyzed. The influence of "error" of calculation of reactivity coefficients is estimated through changes of the maximal temperatures in the basic accident processes at use of various calculational sets of component of feedback reactivity. The acceptability (for the given model) widely used in Russia diffusion calculation method is demonstrated. It testifies the reli-ability of a substantiation of physical parameters of safety in a reactor AI-600 with a hybrid core.

Keywords
calculational deviations, value of reactivity coefficients, reactor AI-600, гhybrid core, component of feedback reactivity, diffusion calculation method

Article Text(in Russian, PDF)

References

UDC 621.039.58

Problems of Atomic Science and Technology. Series: Nuclear Constants, issue 1-2, 2002