Email this article Testing the Filtering Process for Spent Zinc Melt After Removal of Fuel Cladding with the BOR-60 Reactor SNF Nitride
- Authors: Kuzin M.A.1, Makarov A.O.1,2, Lakeev P.V.1
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Affiliations:
- SSC Research Institute of Atomic Reactors
- Dimitrovgrad Engineering and Technological Institute of the National Research Nuclear University MEPhI
- Issue: Vol 52, No 4 (2018)
- Pages: 707-710
- Section: 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
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Abstract
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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About the authors
M. A. Kuzin
SSC Research Institute of Atomic Reactors
Author for correspondence.
Email: distutfuzzy@yandex.ru
Russian Federation, Ulyanovsk oblast, Dimitrovgrad, 433510
A. O. Makarov
SSC Research Institute of Atomic Reactors; Dimitrovgrad Engineering and Technological Institute of the National Research Nuclear University MEPhI
Email: distutfuzzy@yandex.ru
Russian Federation, Ulyanovsk oblast, Dimitrovgrad, 433510; Ulyanovsk oblast, Dimitrovgrad, 433511
P. V. Lakeev
SSC Research Institute of Atomic Reactors
Email: distutfuzzy@yandex.ru
Russian Federation, Ulyanovsk oblast, Dimitrovgrad, 433510
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