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Accessible Unlicensed Requires Authentication Published by De Gruyter December 8, 2016

Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code

Untersuchung des Einflusses von Ultra-Hochtemperatur-Keramiken als Material für Brennstoff-Hüllrohre auf die Reaktorleistung mit Hilfe des SERPENT-Monte-Carlo-Codes
T. Korkut, A. Kara and H. Korkut
From the journal Kerntechnik


Ultra High Temperature Ceramics (UHTCs) have low density and high melting point. So they are useful materials in the nuclear industry especially reactor core design. Three UHTCs (silicon carbide, vanadium carbide, and zirconium carbide) were evaluated as the nuclear fuel cladding materials. The SERPENT Monte Carlo code was used to model CANDU, PWR, and VVER type reactor core and to calculate burnup parameters. Some changes were observed at the same burnup and neutronic parameters (keff, neutron flux, absorption rate, and fission rate, depletion of U-238, U-238, Xe-135, Sm-149) with the use of these UHTCs. Results were compared to conventional cladding material zircalloy.


Ultra-Hochtemperatur-Keramiken (UHTCs) haben eine niedrige Dichte und einen hohen Schmelzpunkt. Sie sind deshalb bei der Auslegung von Reaktorkernen von Vorteil. Drei UHTCs (Siliciumcarbid, Vanadiumcarbid und Zirkoniumcarbid) wurden als Materialien für Brennstoff-Hüllrohre bewertet. Der SERPENT-Monte-Carlo-Code wurde verwendet, um die Reaktorkerne von CANDU-, PWR- und VVER-Anlagen zu modellieren und die Abbrandparameter zu berechnen. Bei Verwendung der UHTC-Materialien wurden bei gleichem Abbrand und gleichen Neutronenparametern (keff, Neutronfluss, Absorptionsrate and Spaltrate, Abreicherung von U-238, U-238, Xe-135, Sm-149) einige Unterschiede festgestellt. Die Ergebnisse wurden verglichen mit dem konventionallen Hüllrohrmaterial Zirkaloy.

* Corresponding author: E-mail:


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Received: 2015-10-05
Published Online: 2016-12-08
Published in Print: 2016-12-16

© 2016, Carl Hanser Verlag, München