On the degradation progression of a BWR control blade under high-temperature steam-starved conditions
High-temperature control blade degradation tests simulating a beginning phase of a severe accident in BWRs has been comprehensively performed in Japan Atomic Energy Agency (JAEA). In the latest test, a mock-up of BWR bundle material has been investigated under postulated Fukushima Dai-Ichi (1F) unit...
Saved in:
| Main Authors: | , , |
|---|---|
| Format: | article |
| Language: | EN |
| Published: |
The Japan Society of Mechanical Engineers
2020
|
| Subjects: | |
| Online Access: | https://doaj.org/article/40f94824f5da4d49bf48827b2aeef709 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
Be the first to leave a comment!