Enviar artigo por via de e-mail Testing the Filtering Process for Spent Zinc Melt After Removal of Fuel Cladding with the BOR-60 Reactor SNF Nitride
- Autores: Kuzin M.A.1, Makarov A.O.1,2, Lakeev P.V.1
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Afiliações:
- SSC Research Institute of Atomic Reactors
- Dimitrovgrad Engineering and Technological Institute of the National Research Nuclear University MEPhI
- Edição: Volume 52, Nº 4 (2018)
- Páginas: 707-710
- Seção: Selected Articles from the Journal Khimicheskaya Tekhnologiya
- URL: https://bakhtiniada.ru/0040-5795/article/view/172396
- DOI: https://doi.org/10.1134/S0040579518040152
- ID: 172396
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Resumo
The results of testing the efficiency of the process of filtering zinc melt obtained after dissolving the fuel rod cladding from the BOR-60 reactor with SNF nitride in a laboratory installation for zinc melt purification from suspended fission products, intermetallic compounds, and fuel particles in the conditions of the protective chamber are presented. The feasibility of filtering for zinc recovery after dissolution of the fuel rod cladding is demonstrated, while considering the ratio of structural materials and zinc corresponding to the tests performed.
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Sobre autores
M. Kuzin
SSC Research Institute of Atomic Reactors
Autor responsável pela correspondência
Email: distutfuzzy@yandex.ru
Rússia, Ulyanovsk oblast, Dimitrovgrad, 433510
A. Makarov
SSC Research Institute of Atomic Reactors; Dimitrovgrad Engineering and Technological Institute of the National Research Nuclear University MEPhI
Email: distutfuzzy@yandex.ru
Rússia, Ulyanovsk oblast, Dimitrovgrad, 433510; Ulyanovsk oblast, Dimitrovgrad, 433511
P. Lakeev
SSC Research Institute of Atomic Reactors
Email: distutfuzzy@yandex.ru
Rússia, Ulyanovsk oblast, Dimitrovgrad, 433510
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