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Reduced Enrichment for Research and Test Reactors
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Abstracts and Available Papers Presented at the
2002 International RERTR Meeting

RESULTS OF IRT-4M TYPE FA’s TESTING
IN THE WWR-CM REACTOR (TASHKENT)

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

E.P.Ryazantsev, P.M.Egorenkov, V.A.Nassonov,
RRC “Kurchatov Institute”, Moscow, Russia.

B.S.Yuldashev, Kh.Kh.Karabaev, A.A.Dosimbaev,
Institute of Nuclear Physics, Tashkent, Uzbekistan.

V.G.Aden, E.F.Kartashev, V.A.Lukichev,
RDIPE, Moscow, Russia.

A.B.Aleksandrov, A.A.Yenin,
JSC NZHK, Novosibirsk, Russia.

ABSTRACT

According to the Russian RERTR Program the life time testing of 4 the IRT-4M type FA (two 8-tube and two 6-tube) with LEU (19.7%) UO2-Al fuel in the WWR-CM reactor (Tashkent, Uzbekistan) were carried out. Uranium density in the Fuel Elements (FE) meat – 3.0 g/cm3. These FA were fabricated by “Novosibirsk Chemical Concentrates Plant” (NZHK). In the end November 2000 the IRT-4M type FA testing were begun. At the beginning FA were located in central cells of the WWR-CM reactor core. After completion of sixth cycle of IRT-4M type FA testing FA were reloaded in peripheral cells of the core. Testing of IRT-4M type FA was ended in March 2002, after completion of sixteenth cycle testing. The average fuel burnup in FA reached of 60.0–66.5%, and maximum fuel burnup – 83–92.6%. Calculated heat fluxes at fuel element surface reached more 600 kW/m2, clad temperature – 85˚C. Results of continuous monitoring of gas activity in air under reactor cover and daily monitoring of water activity in primary circuit give basis to consider that under testing of IRT-4M type FA clad failure of fuel elements was not.


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