Publication Date:
2019-04-01
Description:
There are results of long-term thermal aging of samples of irradiated and nonirradiated FA jacket and nonirradiated fuel element cladding at a temperature range from 300 to 550°C in argon, to 600°C in air. Materials have been studied before and after thermal tests. The forecast estimation of expected corrosion damage of barrier material at the radionuclide release from spent fuel assemblies of BN-350 reactor into environment during dry storage for 50 years was carried out.
Print ISSN:
1687-6075
Electronic ISSN:
1687-6083
Topics:
Energy, Environment Protection, Nuclear Power Engineering
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