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Conference Article: Irradiation creep of austenitic steels irradiated up to high fluence in the BOR-60 reactor

Abstract

This gas-pressurized tube experiment was conducted in Row 6 of the BOR-60 reactor. The rate of damage dose was varied with the height of specimen from 3 to 6*10^-7 dpa/sec. During 11 years of irradiation the maximum neutron fluence was 21.8*10²⁶ m^-2 E>0.1 MeV (100 dpa). Each tube was 200 mm long, 6.0 or 6.9 mm inner diameter and 0.3 or 0.4 mm thick. It ws specified seven values of stress varied from 0 to 320 MPa at irradiation temperature -420 deg. C. During reloading the tubes were taken out of the reactor to measure their deformation. The swelling rate of nondepressurized specimens on the basis of 16Cr-15Ni-3Mo-Nb steel was decreased with increasing the carbon and boron content under irradiation up to fluence 21.8*10²⁶m^-2 (E>0.1 MeV) at temperature 420 deg. C. The rate of irradiation creep on investigated steels was rather exactly defined by the equation epsilon/sigma=B(sigma)=B_o+D*S, at the values of Bo and D Coefficients 1*10^-6 (MPa*dpa)^-1 and (0.3-1.02)*10^-2 Mpa^-1, respectively. The coefficients are in well agreement with similar coefficients of another steels attributed to austenitic type.

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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:179-188