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Testing of the IRT-4M type FA with LEU UO 2 -Al fuel in WWR-CM reactor

E. P. RyazantsevP.M. EgorenkovV.A. NassonovA.V. TalievA.D. GerstleA.A. KarpukhinRRC 'Kurchatov Institute' 123060 Moscow (Russian Federation)V.M. ChernyshovJSC 'TVEL', Moscow (Russian Federation)B. S. YuldashevT. B. AshrapovA. A. DosimbaevInstitute of Nuclear Physics, Tashkent (Uzbekistan)
2000en
ABI

Аннотация

Now in the WWR-CM reactor (Tashkent) the IRT-3M type Fuel Assemblies (FA) with UO{sub 2}-Al fuel of 36% enrichment are used. Density of uranium in the Fuel Elements (FE) meats - 2.5 g/cm{sup 3}. Thickness of meats - 0.5 mm. The WWR-CM reactor conversion on use of these FA was begun in August, 1998 and was completed in February, 1999. According to the Russian RERTR program in the WWR-CM reactor the lifetime testing of four IRT-4M type FA (two 8-tube and two 6-tube) with LEU (19.7%) UO{sub 2}-Al fuel will be carried out. These FA were fabricated by JSC 'Novosibirsk Chemical Concentrates Plant' (NZHK). Uranium density in the FE meats - 3.0 g/cm{sup 3}. FE cladding material in two FA is aluminum alloy CAB-1, and in two others - alloy AM{gamma}2. Neutronic and thermal-hydraulic calculations in a substantiation of safety of the IRT-4M type FA testing were performed. Results of calculations are presented. The IRT-4M type FA testing will be begun in October, 2000. (author)

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