Properties of zirconium alloys and their applications in light water reactors (LWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 118

80

Irradiated: 1.6-9.5 × 10 25 n/m 2
Unirradiated

60

40

20

0

0 250 500

Hydrogen, ppm

750 1000

80

60

40

20

0

0 250 500

Hydrogen, ppm

750 1000

80

60

40

￿ ￿ ￿ ￿ ￿ ￿

20

0

0 250 500

Hydrogen, ppm

750 1000

4.30 Uniform (top) and total elongation (middle) and reduction of area
(bottom) as a function of hydrogen for unirradiated and irradiated
Zircaloy-2 tested at 332 ° C (605K) (circumferential hydrides) (Wisner &
Adamson, 1998).