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Irradiation Test of MOX Fuel Rods Fabricated by Attrition-Milling and Analysis of In-Pile Data with COSMOS Code

Byung-Ho Lee, Yang-Hyun Koo, Han-Soo Kim, Jae-Yong Oh, Young-Woo Lee, Dong-Seong Sohn, Wolfgang Wiesenack

Nuclear Technology / Volume 172 / Number 3 / December 2010 / Pages 246-254

Technical Paper / Fuel Cycle and Management /

Attrition-milling technology for fabricating mixed oxide (MOX) fuel was developed to mix the plutonium in UO2 fuels as homogeneously as possible. The fabricated MOX fuels were instrumented with temperature and pressure gauges that enabled one to measure the fuel temperature and rod internal pressure online. An irradiation test in the Halden reactor was performed to investigate the in-pile behavior of the fabricated MOX fuel. The irradiation of 1020 effective full-power days was successfully accomplished with good integrity of the test fuel rods. The rod average burnup reached [approximately]50 MWd/kg HM, and the measured fuel centerline temperature was [approximately]1000°C for the MOX fuels. A significant fission gas release was observed due to the high power level. The online measured in-pile performance data of the two attrition-milled MOX fuel rods were analyzed and compared with the fuel performance code COSMOS. COSMOS simulated the fuel centerline temperature and rod internal pressure for both MOX fuel rods. The analysis by COSMOS showed good agreement with the online measured in-pile behavior of MOX fuel.

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