Výsledky vyhledávání - "Yu Daichenkova"

RADIATION SAFETY EVALUATION OF A TRANSPORT CONTAINER DURING CARTING SPENT NITRIDE URANIUM-PLUTONIUM FUEL OF BN-600 USING THE MCU-FR CODE

Autor: D Shkarovskiy, Yu Daichenkova, A Bikeev, A Belov

Publikováno v: PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS. 2020:85-95

At present, the BN-600 and BN-800 reactors are used for tests of experimental fuel assemblies containing MOX and MNUP fuels. For transportation of spent fuel assemblies of BN-600 with mixed nitride uranium-plutonium fuel is planned to use a regular t

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::175e264e55e2708222b46926a05c7a79
https://doi.org/10.55176/2414-1038-2020-2-85-95

Zobrazit plný text záznamu

DEVELOPMENT AND TESTING OF FULL-SCALE MATHEMATICAL MODEL OF A TRANSPORT CONTAINER FOR RADIATION SAFETY EVALUATION BY THE MONTE-CARLO METHOD DURING CARTING SPENT FUEL OF VVER-1000 AND VVER-1200

Autor: D Shkarovskiy, D Oleynik, M Kalugin, Yu Daichenkova, A Bikeev

Publikováno v: PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS. 2019:67-78

In recent years, new approaches have been developed to ensure radiation safety during carting spent nuclear fuel from nuclear power plants with VVER-1000 and VVER-1200 reactors, because the height of the fuel assembly and the initial enrichment of fu

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::2aca35ea76bd2b922b204e294005d21c
https://doi.org/10.55176/2414-1038-2019-4-67-78

Zobrazit plný text záznamu

Vyhledávací nástroje:

Upřesnit hledání