HTGR Knowledge Base

Conference Article: Development and Calculation of Neutronic Benchmark Models For The GT-MHR Type Reactor Cells

V. Boyarinov, E. Glushkov, V. Davidenko, P. Fomichenko, V. Tsibulsky, RRC Kurchatov Institute, Moscow, RUSSIA; E. Marova, Yu. Sukharev, OKBM, Nizhny Novgorod, RUSSIA; E. Mitenkova, N. Novikov, IBRAE, Moscow, RUSSIA

Abstract

Absence of relevant neutronic experimental data substantiating the use of plutonium fuel in high-temperature graphite moderated reactors determines the necessity of conducting the step-by-step calculational benchmark studies of neutron-physics characteristics of HTGR reactors supposing the use of Pu fuel. In frames of proposed benchmark neutronic calculations of elementary cells of a HTGR with prismatic block fuel, the benchmark models of fuel compact and burnable poison cells were developed and calculated. This paper presents a short description of benchmarks and currently available solutions.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Proceedings of the Conference on High Temperature Reactors, Beijing, China, September, 22-24, 2004
International Atomic Energy Agency, Vienna (Austria)
HTR-2004, pp:1-18