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
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
Ye. F. Kartashov, V. A. Lukichev
Research and Development Institute of Nuclear Energy and Industry
P. O. Box 788, 107014, Moscow, Russia
V. M. Troyanov, A. A. Enin, A. A. Tkachev
119017, ul. B. Ordinka 24/26, Moscow, Russia
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.
Full paper in PDF format
- The Technique and
Preliminary Results of LEU U-Mo Full Size IRT Type
Fuel Testing in the MIR Reactor, A.L. Izhutov et al.
[PDF, 483KB, 8 pages]
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Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161