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...
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| Autores principales: | , , |
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| Formato: | article |
| Lenguaje: | EN |
| Publicado: |
The Japan Society of Mechanical Engineers
2020
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| Acceso en línea: | https://doaj.org/article/40f94824f5da4d49bf48827b2aeef709 |
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