Kakiuchi, Kazuo 
; Amaya, Masaki 
The irradiation growth behavior of the improved Zr alloys for light-water reactor fuel cladding was investigated. The coupon specimens, which were prepared from fuel cladding tubes with improved Zr alloys, had been irradiated in the Halden reactor in Norway at temperatures of 300 and 320
C under a typical water chemistry condition of PWR and 240C under the coolant condition of the Halden reactor up to a fast neutron fluence of 
8
10
(n/cm
, E 
1 MeV). During and after the irradiation test, the amount of irradiation growth of each specimen was evaluated. The effect of the difference in alloy composition on irradiation growth behavior seemed insignificant if the other conditions e.g. the final heat treatment condition at fabrication, irradiation temperature and the amount of hydrogen pre-charged in the specimen were the same.
Language |
: | Japanese |
|---|---|---|
Journal |
: | |
Volume |
: | 19 |
Number |
: | 1 |
Pages |
: | p.24 - 33 |
Publication Year/Month |
: | 2020/03 |
Paper URL |
: |
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Keywords |
: | no keyword |
Cooperating Institute |
: |
Accesses |
: |
- Accesses |
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Altmetrics |
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