Properties of zirconium alloys and their applications in light water reactors (LWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 95

Dislocation density, x 10 − 14 m − 2

10

9

8

7

6

5

4

3

2

1 Unirrad. H737 NRU OSIRIS CANDU

0

0 1 2 3 4 5

Fast-neutron fluence, × 10 − 25 n/m − 2

6 7 8 9 10

4.9 Variation of <a> type dislocation loops as a function of fl uence in
various reactors at 250-290 ° C (523-563K). (Source: Reprinted, with
permission, from Davies et al . (1994), copyright ASTM International,
100 Barr Harbor Drive, West Conshohocken, PA 19428.)

3.0

Measured from
TEM images

UHFP Present study
Unpublished GE work, 1998
Unpublished GE work, 1997

2.5

2.0

1.5

￿ ￿ ￿ ￿ ￿ ￿

1.0

Slope = 7.5 × 10 − 13 n − 1

0.5

0.0

0 10 20 30 40

Fluence/10 25 nm − 2

4.10 Variation of <c> type dislocation density as a function of fl uence
for Zircaloy-2 irradiated at 290 ° C (563K). (Source: Reprinted, with
permission, from Mahmood et al . (2000), copyright ASTM International,
100 Barr Harbor Drive, West Conshohocken, PA 19428.)