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Abstract
In terms of safety, nuclear fuel cladding is one of the main barriers in preventing the release of radioactive materials to the environment.The integrity of the fuel cladding is essential both in operation and in the long-term storage of spent nuclear fuel, not to mention accident conditions.In this paper, we review shortlyrelevantaccident tolerant cladding materialsfrom the Finnish point of view. Features compared to the traditional Zr-alloy cladding in the areasof oxidation, hydrogen pick-up,mechanical behaviourand fuel performance modellingare considered.
Original language | English |
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Title of host publication | SYP2019 Proceedings |
Publisher | Finnish Nuclear Society |
Number of pages | 4 |
Publication status | Published - 31 Oct 2019 |
MoE publication type | A4 Article in a conference publication |
Event | Nuclear Science and Technology Symposium, NST 2019 - Helsinki, Finland Duration: 20 Oct 2019 → 31 Oct 2019 |
Conference
Conference | Nuclear Science and Technology Symposium, NST 2019 |
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Abbreviated title | NST 2019 |
Country/Territory | Finland |
City | Helsinki |
Period | 20/10/19 → 31/10/19 |
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INFLAME: Interdisciplinary Fuels and Materials
Arkoma, A. (Participant), Heikinheimo, J. (Participant), Huotilainen, C. (Participant), Kärkelä, T. (Participant), Loukusa, H. (Manager), Peltonen, J. (Participant), Penttilä, S. (Participant), Pohja, R. (Participant) & Sipilä, K. (Participant)
1/01/19 → …
Project: Other