2007 International RERTR Meeting

Abstracts and Available Papers Presented at the Meeting

The Technique and Preliminary Results of LEU U-Mo Full Size IRT Type Fuel Testing in the MIR Reactor

A. L. Izhutov, V. A. Starkov, V.V. Pimenov, V. Ye. Fedoseev
Research Reactor Complex,
RIAR, 433510, Dimitrovgrad-10, Ulyanovsk Region - Russia
and
I. V. Dobrikova, A. V. Vatulin, V. B. Suprun
A.A. Bochvar All-Russian Scientific Research Institute of Inorganic Materials
P. O. Box 369, 123060, Moscow, Russia
and
Ye. F. Kartashov, V. A. Lukichev
Research and Development Institute of Nuclear Energy and Industry
P. O. Box 788, 107014, Moscow, Russia
and
V. M. Troyanov, A. A. Enin, A. A. Tkachev
OAO "TVEL"
119017, ul. B. Ordinka 24/26, Moscow, Russia

ABSTRACT

In March 2007 in-pile testing of LEU U-Mo full-size IRT type fuel elements was started in the MIR reactor. Four prototype fuel elements for Uzbekistan WWR SM reactor are being tested simultaneously - two of tube type design and two of pin type design. The dismountable irradiation devices were constructed for intermediate reloading and inspection of fuel elements during reactor testing. The objective of the test is to obtain the experimental results for determination of more reliable design and licensing fuel elements for conversion of the WWR SM reactor. The heat power of fuel elements is measured on-line by thermal balance method. The distribution of fission density and burn-up of uranium in the volume of elements are calculated by using the MIR reactor MCU code (Monte-Carlo) model. In this paper the design of fuel elements, the technique, main parameters and preliminary results are described.

 

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