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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Boyarinov V.F.1, Fomichenko P.A.1, Ternovykh M.Yu.2
1National Research Centre "Kurchatov Institute", Moscow, Russia
2National Research Nuclear University "MEPhI", Moscow, Russia

Abstract

The research was implemented under the IAEA coordinated research project “Uncertainty analysis in HTGR modeling”. The principal goal of the project was the development of guidance for tracking the propagation uncertainties of various origins when modeling neutronics, thermal hydraulics and fuel burnup, as well as testing the respective computational tool. One of the requirements in the course of performing a neutronics part of the project is the application of covariance matrices of the SCALE code. This paper describes the first stage of the neutronics calculation, namely, the calculation of single-group interaction cross-section uncertainties for the basic isotopes of the reactor cells with prismatic MHTGR-350 fuel blocks, in particular for 235U and 238U isotopes.

Key words
SCALE-6.0 code, multigroup microcross-section library, covariance matrix, uncertainty, interaction cross-sections, prismatic fuel block, benchmark, isotope nuclear density, neutron flux

Article Text (PDF, in Russian)

References

UDC 004.94:681.3.06

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, issue 1:7, 2015