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Conference Article: Program of GT-MHR Fuel Development and Justification

N. Kodochigov, Yu. Sukharev, OKBM, RUSSIA; N. Ponomarev-Stepnoy, Yu. Degaltsev, RCC KI, RUSSIA; V. Novikov, I. Kadarmetov, V. Makarov, VNIINM, RUSSIA; V. Sulaberidze NIIAR, RUSSIA; A. Chernikov, SPA Lutch, RUSSIA; D. Mc Eachern, R. Noren, GA, USA

Abstract

The design of the Gas-Turbine Modular Helium Reactor (GT-MHR) is based on rendering the excess weapons-grade plutonium useless for weapons by destroying a large fraction of the fissionable plutonium in a single pass through the reactor. This requires a fuel that can achieve a high burnup of fissionable plutonium in case of fission product release under normal operating conditions and in design-basis accidents at the level allowed for modular reactors with direct gas-turbine cycle.

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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:1-9