METHOD FOR EVALUATING THRESHOLD COEFFICIENT OF IRRADIATED ZIRCONIUM ALLOY STRESS INTENSITY ON FUEL-ELEMENT CANS Russian patent published in 2007 - IPC G21C17/00 

FIELD: studying material properties for nuclear reactors.

SUBSTANCE: proposed method used to investigate impact of chemical composition, texture, manufacturing technique, and irradiation of zirconium alloys of nuclear reactor fuel element cans onto their corrosion cracking resistance in support of fuel element serviceability in case of reactor power variations includes removal of coupons of tubular specimens and reference specimens from fuel element can, cracking of inner surfaces of tubular specimens and reference specimens, testing of tubular specimens for long-time endurance by internal gas pressure in corrosive material environment, measurement of crack depth on reference specimens, whereupon initial coefficient of stress intensity is calculated. Curve illustrating rate of crack growth as function of initial coefficient of stress intensity is constructed to evaluate threshold coefficient of stress intensity.

EFFECT: reduced cost, facilitated procedure, enhanced reliability of investigation results.

8 cl, 1 dwg