Argonne National Laboratory
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Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
2000 International RERTR Meeting

TESTING OF THE IRT-4M TYPE FA WITH LEU UO2-Al FUEL
IN WWR-CM REACTOR

E.P.Ryazantsev, P.M.Egorenkov, V.A.Nassonov, A.V.Taliev,
A.D.Gerstle, A.A.Karpukhin,

RRC “Kurchatov Institute”

V.M.Chernyshov,
JSC “TVEL”, Moscow, Russia

B.S.Yuldashev, T.B.Ashrapov, A.A.Dosimbaev,
Institute of Nuclear Physics, Tashkent, Uzbekistan

ABSTRACT

Now in the WWR-CM reactor (Tashkent) the IRT-3M type Fuel Assemblies (FA) with UO2-Al fuel of 36% enrichment are used. Density of uranium in the Fuel Elements (FE) meats – 2.5 g/cm3. 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%) UO2-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/cm3. FE cladding material in two FA is aluminum alloy CAB-1, and in two others – alloy AMг2. 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.


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Contact:
Mr. Pavel M. Egorenkov
Head of Laboratory
Reactor Technology & Materials Research
Kurchatov Institute
Kurchatov Square 1
123182, Moscow, Russia

Phone: 7 (095) 196-9120
Fax: 7 (095) 196-4588

2016 RERTR Meeting

The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium. Stay tuned for further details.

2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.

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Last modified on July 29, 2008 11:33 +0200