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Characterization measurements of fluental and graphite in FiR1 TRIGA research reactor decommissioning waste
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Thông tin tài liệu:
The objective of this article is to study the activities and special characteristics of graphite and Fluental neutron moderator material in FiR1 TRIGA Mark II type research reactor in Finland. Quantifying the nuclide vector and total activities of decommissioning waste is a legal requirement and provides input to many other aspect of decommissioning project.
Nội dung trích xuất từ tài liệu:
Characterization measurements of fluental and graphite in FiR1 TRIGA research reactor decommissioning waste
Nội dung trích xuất từ tài liệu:
Characterization measurements of fluental and graphite in FiR1 TRIGA research reactor decommissioning waste
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Nuclear engineering and design Characterization measurements Fluental neutron moderator material Nuclide vector Point-depletion code modellingTài liệu liên quan:
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