Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Current status of studies on FR fuel and structural materials in the Russian Federation

Poplavsky, V.M.;Zabudko, L.M. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))

Abstract

Review is made on the principle factors which restrict the BN fuel life time: dimensional changes of wrappers and cladding due to steel swelling and irradiation creep. Fuel-cladding mechanical and chemical interaction, fuel mass transfer, deterioration of mechanical properties of cladding steel under irradiation. The information on the programs of structural materials development is given. The main results on the advanced BN fuel development are presented.

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key words: Fast Neutron Spectrum Systems, Nuclear Technology
Reference:
Influence of high dose irradiation on core structural and fuel materials in advanced reactors. Technical committee meeting, Obninsk (Russian Federation), 16-19 Jun 1997
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1039, pp:7-14