Results of U0.55Pu0.45N and U0.4Pu0.6N mixed mononitride fuel tests in a bor-60 reactor to burnup 12% h.a

Autor:	O. N. Nikitin, B. D. Rogozkin, Yu. E. Fedorov, M. G. Shishkov, F. N. Kryukov, A. V. Belyaeva, L. M. Zabudko, N. M. Stepennova, S. V. Kuz’min
Rok vydání:	2011
Předmět:	Cladding (metalworking) Fission products Materials science Nuclear engineering Metallurgy chemistry.chemical_element Nuclear Energy and Engineering chemistry medicine Irradiation Swelling medicine.symptom Porosity Helium Power density Burnup
Zdroj:	Atomic Energy. 110:412-429
ISSN:	1573-8205 1063-4258
Popis:	The results of post-reactor studies of U0.55Pu0.45N and U0.4Pu0.6N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively, with power density 430 and 540 W/cm. All fuel elements remained hermetic; the ChS-68 steel cladding (20% cold deformation) retained excess plasticity. The maximum zone of interaction between the cladding and the fuel and fission products did not exceed 15 μm. The swelling rate of U0.4Pu0.6N and U0.55Pu0.45N fuel was 1.1 and 0.68%/% burnup, respectively. The gas release did not exceed 19.3 and 19%. The steel damage dose was 43 dpa. The character of the porosity distribution in the fuel affects the swelling and gas release.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::e84f35492eee00f008dc2f10899a4dc2 https://doi.org/10.1007/s10512-011-9442-0 Zobrazit plný text záznamu Full text from SpringerLink