Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor

The results of an investigation of gas release and swelling of uranium mononitride fuel after irradiation in standard and experimental fuel assemblies in the BR-10 reactor in the burnup range 3.4–8.4% h.a. are presented and analyzed. The results obtained were used to verify the fuel code DRAKON.

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Bibliographic Details
Published inAtomic energy (New York, N.Y.) Vol. 121; no. 6; pp. 415 - 423
Main Authors Porollo, S. I., Ivanov, S. N., Marinenko, E. E., Zabud’ko, L. M.
Format Journal Article
LanguageEnglish
Published New York Springer US 01.04.2017
Springer
Springer Nature B.V
Subjects
Analysis
Data processing
Energy industry
Hadrons
Heavy Ions
Industrial accidents
Irradiation
Nitrides
Nuclear Chemistry
Nuclear Energy
Nuclear fuels
Nuclear Physics
Nuclear power plants
Nuclear reactors
Physics
Physics and Astronomy
Production planning
Radiation
Reactors
Swelling
Uranium
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Summary:The results of an investigation of gas release and swelling of uranium mononitride fuel after irradiation in standard and experimental fuel assemblies in the BR-10 reactor in the burnup range 3.4–8.4% h.a. are presented and analyzed. The results obtained were used to verify the fuel code DRAKON.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-017-0221-4