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: Anton PSHENICHNIKOV, Yuji NAGAE, Masaki KURATA
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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