Analyzing the causes for the dispersion of the fast reactor spent fuel rod cladding properties
The swelling, corrosion and high-temperature embrittlement behavior of the fast-neutron sodium-cooled reactor standard and test fuel rod claddings was studied following the operation up to a damaging dose of 55 to 69 dpa. The tested characteristics were found to differ sensitively...
| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
National Research Nuclear University (MEPhI)
2019-12-01
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| Series: | Nuclear Energy and Technology |
| Subjects: | |
| Online Access: | https://nucet.pensoft.net/article/48423/download/pdf/ |