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Conference Article: Post-irradiation examination of Ti or Nb stabilized austenitic steels irradiated as BN-600 reactor fuel pin claddings up to 87 dpa

Abstract

The results of postirradiation study of fuel pins with claddings fabricated from the 16Cr-15Ni-3Mo-Nb (EI-847), 16Cr-15Ni-3Mo-Nb-B (EP-172) and 16Cr-15Ni-2Mo-Ti-V-B (ChS-68) austenitic stainless steels in 20% cold-work condition are given. All fuel pins after irradiation in the BN-600 reactor to peak burn up of 11.6% (displacement dose of 83 dpa) and remained its tightness. At the same time, a number of fuel pins have failed during low-load handling in hot cells. Tensile mechanical tests revealed a drastic decrease in strength and a severe embrittlement of the cladding material taken from some parts of fuel pins. For these parts numerous deep microcracks at the inner surface of pin cladding have been observed. Locations of the maximum cladding property degradation coincides with locations of the peak diameter increase and peak swelling. The effects of high swelling and radiation-induced segregation on mechanical properties and corrosion resistance of the fuel pin cladding are discussed.

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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:145-151