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Conference Article: In-pile strength of austenitic steels for fast reactors fuel pin cladding

Popov, V.V. (Institute of Physics and Power Engineering, State Scientific Center, Obninsk (Russian Federation))

Abstract

The main mechanism of deformation of a fast reactor fuel pin clad under loading is in-pile creep. Depending upon the value of stress and temperature in a clad, two mechanisms of deformation may be realized: intergranular creep and intragranular dislocation creep, respectively at low stresses and at higher stresses. Intergranular creep is accompanied either by formation of growth of pores along grain boundaries (at T_irr>0.5 T_melt) or by arising and development of cracks at grain triad joints (at higher temperatures). Formation of pores and cracks occurs as the stress exceeds a certain threshold value. The level of failure stresses in the course of reactor operation has been computed in relation to behaviour of an austenitic steel as a fuel pin clad material.

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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:231-238