Spark Plasma Sintering of Fuel Cermets for Nuclear Reactor Applications
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Spark Plasma Sintering of Fuel Cermets for Nuclear Reactor Applications Yang Zhong1, 2, Robert C. O’Brien1, Steven D. Howe1, Nathan D. Jerred1, Kristopher Schwinn1, Laura Sudderth1 and Joshua Hundley1 1
Center for Space Nuclear Research, Idaho National Laboratory, ID 83415, U.S.A. Department of Chemical, Materials and Biomolecular Engineering, University of Connecticut, CT 06269, U.S.A.
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ABSTRACT The feasibility of the fabrication of tungsten based nuclear fuel cermets via Spark Plasma Sintering (SPS) is investigated in this work. CeO2 is used to simulate fuel loadings of UO2 or Mixed-Oxide (MOX) fuels within tungsten-based cermets due to the similar properties of these materials. This study shows that after a short time sintering, greater than 90 % density can be achieved, which is suitable to possess good strength as well as the ability to contain fission products. The mechanical properties and the densities of the samples are also investigated as functions of the applied pressures during the sintering. INTRODUCTION The Center for Space Nuclear Research (CSNR), located in Idaho Falls, ID and operated by Universities Space Research Association (USRA) and Idaho National Laboratory (INL), with a wealth of experience in research and development of advanced space nuclear systems, including power and propulsion systems, and radioisotope power generators, has been very active in creating opportunities for university researchers to collaborate with their counterparts at NASA, INL and other DOE labs. CSNR has devoted extensive effort on the fabrication of tungsten based nuclear cermets for nuclear reactors for space exploration application. During the 2011 summer fellowship program of CSNR, tungsten based nuclear cermets have been fabricated via Spark Plasma Sintering (SPS) process. The tungsten based nuclear cermets fabricated by SPS will not only be applicable for the space exploration application but also for the ground based nuclear reactors. This paper focuses on the cermets for ground based nuclear reactor applications. Nuclear energy contributes ~20 % of the total electricity consumed in the United States[1]. However, the energy production process, i.e., nuclear fission, produces high level of radioactive fission products. Under some extreme conditions, these fission products may disperse into the atmosphere, such as the recent events in Fukishima, Japan. This revealed a need for a high temperature fuel form that will not melt down from decay heat after a loss of coolant accident. Furthermore, the fuel material should contain the fission products from dispersion during a combination of accidental high temperature excursions and steam/hydrogen explosions. W-UO2 cermet fuels are of particular interest these days due to its ability to contain fission products when increased operational safety and security are demanded. The traditional fabrication techniques (including hot isostatic pressing or hipping, pressure-less sintering, etc), which require very high processing temperature and long sintering time, had been ut
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