Properties of zirconium alloys and their applications in light water reactors (LWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 111

1.0

0.9

Irradiated Zircaloy
2.2

10 21 n/cm 2
523K

×

0.8

0.7

0.6

0 5 10 15 20 25

Distance along gauge length, mm

4.23 Deformation expressed as ratio of cross sectional area to original
area measured along the specimen gauge length (Williams et al ., 1974).

7

Irradiated zircaloy
Strain rate: 3.33-83.3 × 10 − 5 s − 1
Fluence: 1.3-11

6

10 21 n/cm 2
Test temp: 561-623K

×

5

4

3

2

Best estimate

1

￿ ￿ ￿ ￿ ￿ ￿

0

0 5 10 15

Nominal gauge length, mm

20 25 30

4.24 Effect of specimen gauge length on uniform elongation.
(Source: Reprinted, with permission, from Adamson et al . (1986),
copyright ASTM International, 100 Barr Harbor Drive, West
Conshohocken, PA 19428.)

basically the same material. These data show that strain values developed
for use as failure criteria or strain limits are not real material properties, but
are strongly infl uenced by the specimen design used to obtain the data.
For burst tests of irradiated materials at 350°C (623K) (Onimus et al .,
2004) careful laser imaging measurements indicate that tubing deformed