Мақаланы E-mail арқылы жіберу Testing the Filtering Process for Spent Zinc Melt After Removal of Fuel Cladding with the BOR-60 Reactor SNF Nitride
- Авторлар: Kuzin M.A.1, Makarov A.O.1,2, Lakeev P.V.1
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Мекемелер:
- SSC Research Institute of Atomic Reactors
- Dimitrovgrad Engineering and Technological Institute of the National Research Nuclear University MEPhI
- Шығарылым: Том 52, № 4 (2018)
- Беттер: 707-710
- Бөлім: Selected Articles from the Journal Khimicheskaya Tekhnologiya
- URL: https://journals.rcsi.science/0040-5795/article/view/172396
- DOI: https://doi.org/10.1134/S0040579518040152
- ID: 172396
Дәйексөз келтіру
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Аннотация
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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Авторлар туралы
M. Kuzin
SSC Research Institute of Atomic Reactors
Хат алмасуға жауапты Автор.
Email: distutfuzzy@yandex.ru
Ресей, 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
Ресей, Ulyanovsk oblast, Dimitrovgrad, 433510; Ulyanovsk oblast, Dimitrovgrad, 433511
P. Lakeev
SSC Research Institute of Atomic Reactors
Email: distutfuzzy@yandex.ru
Ресей, Ulyanovsk oblast, Dimitrovgrad, 433510
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