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Conference Article: A problem to determine short term mechanical properties changes of ferrite-martensite and austenitic steels as materials of fuel assembly of fast reactors under high dose neutron irradiation

Kozolov, A.V.;Averin, A.S.;Brushkova, S.V. (Research and Development Inst. of Power Engineering, Zarechny, Sverdlovsk (Russian Federation));Kalashnic, G.V. (All Russian Research and Scientific Inst. of Inorganic Materials, Moscow (Russian Federation))

Abstract

The results of mechanical tests of flat and ring-shaped samples of two ferrite-martensite steels C0.1-Cr13-Mo2-Nb-V-W and C0.1-Cr12-Mo-Nb-V-W irradiated to different damage doses (up to 100 dpa) have been performed in this work. It have been shown that values of plasticity and strength characteristics determined on this sample types are different. Specific elongation takes the values 8-12% for the flat samples, at the same time, t takes the values 1-3% for the ring-shaped samples at room temperature. A character of fluence dependence of mechanical properties is identical. The steels show viscous damage in all tests. Samples of fuel pin cladding fabricated from the austenitic steel C0.1-Cr16-Ni15-Mo3 were also investigated after there working out in BN-600 reactor up to 76 dpa. Ring-shaped samples were tested at standard single-axle tension. Tube samples were tested by internal pressure of solid filler. All samples were fabricated from one and the same section, mechanical properties obtained are different. Specific elongation of the brittlest section of fuel pin was 0-0.9% for the ring-shaped samples and 2-7% for the tube samples at room temperature. Fractographic investigations were carried out on the samples after mechanical tests. Possible reasons of such difference have been discussed in the work.

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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:211-221