Numerical simulation of mixed oxide fuel burnup taking account of double heterogeneity

The results of a numerical simulation of the burnup of mixed oxide fuel in VVER-1000 taking account of double heterogeneity are presented. The fuel consists of two different materials: a depleted uranium matrix with small amounts of plutonium and agglomerates consisting of particles with an elevated...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2009, Vol.106 (1), p.33-36
Main Authors: Kalugin, M. A., Kuznetsov, V. I.
Format: Article
Language:English
Subjects:
Depleted uranium
Energy
Hadrons
Heat treating
Heavy Ions
Helium
Heterogeneity
Krypton
Nuclear Chemistry
Nuclear Energy
Nuclear Physics
Physics
Physics and Astronomy
Plutonium
Simulation
Uranium
Xenon
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Summary:The results of a numerical simulation of the burnup of mixed oxide fuel in VVER-1000 taking account of double heterogeneity are presented. The fuel consists of two different materials: a depleted uranium matrix with small amounts of plutonium and agglomerates consisting of particles with an elevated plutonium concentration. An important problem is taking double heterogeneity into account correctly, making it possible to evaluate the ratio of the energy release over the fuel-element pellet. Numerical results are obtained for the burnup distribution, energy release, and the concentrations of helium, krypton, and xenon over the radial zones of a fuel element depending on the average fuel burnup over the pellet. The MCU-REA program with the ORIMCU module for calculating burnup was used to perform the calculations.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-009-9127-0