Email this article Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor
- Authors: Porollo S.I.1, Ivanov S.N.1, Marinenko E.E.1, Zabud’ko L.M.2
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Affiliations:
- State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
- Innovation-Technology Center for Project Breakthrough (ITTsP Proryv)
- Issue: Vol 121, No 6 (2017)
- Pages: 415-423
- Section: Article
- URL: https://journal-vniispk.ru/1063-4258/article/view/248329
- DOI: https://doi.org/10.1007/s10512-017-0221-4
- ID: 248329
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Abstract
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.
About the authors
S. I. Porollo
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk
S. N. Ivanov
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk
E. E. Marinenko
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk
L. M. Zabud’ko
Innovation-Technology Center for Project Breakthrough (ITTsP Proryv)
Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow
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