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原文传递 An Overview of Current and Past W-UO[2] CERMET Fuel Fabrication Technology

题名：	An Overview of Current and Past W-UO[2] CERMET Fuel Fabrication Technology
作者：	Steven D. Howe;James E. Werner;Daniel M. Wachs;Douglas E. Burkes;
关键词：	CERMETS; Fuel Development; Nuclear Thermal Propulsion11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AGE ESTIMATION; BONDING; BRAZING; BURNUP; CERMETS; FABRICATION; FISSION PRODUCTS; FUEL ELEMENTS; GRAIN GROWTH; HOT PRESSING; IRRADIATION; MICROSPHERES; NUCLEAR POWER; PROPULSION; ROCKETS; SINTERING; STOICHIOMETRY; SYNTHESIS; TRANSIENTS; TRANSITION TEMPERATURE
摘要：	Studies dating back to the late 1940s performed by a number of different organizations and laboratories have established the major advantages of Nuclear Thermal Propulsion (NTP) systems, particularly for manned missions. A number of NTP projects have been initiated since this time; none have had any sustained fuel development work that appreciably contributed to fuel fabrication or performance data from this era. As interest in these missions returns and previous space nuclear power researchers begin to retire, fuel fabrication technologies must be revisited, so that established technologies can be transferred to young researchers seamlessly and updated, more advanced processes can be employed to develop successful NTP fuels. CERMET fuels, specifically W-UO2, are of particular interest to the next generation NTP plans since these fuels have shown significant advantages over other fuel types, such as relatively high burnup, no significant failures under severe transient conditions, capability of accommodating a large fission product inventory during irradiation and compatibility with flowing hot hydrogen. Examples of previous fabrication routes involved with CERMET fuels include hot isostatic pressing (HIPing) and press and sinter, whereas newer technologies, such as spark plasma sintering, combustion synthesis and microsphere fabrication might be well suited to produce high quality, effective fuel elements. These advanced technologies may address common issues with CERMET fuels, such as grain growth, ductile to brittle transition temperature and UO2 stoichiometry, more effectively than the commonly accepted 鈥榯raditional鈥?fabrication routes. Bonding of fuel elements, especially if the fabrication process demands production of smaller element segments, must be investigated. Advanced brazing techniques and compounds are now available that could produce a higher quality bond segment with increased ease in joining. This paper will briefly address the history of CERMET fuel fabrication technology as related to the GE 710 and ANL Nuclear Rocket Programs, in addition to discussing future plans, viable alternatives and preliminary investigations for W-UO2 CERMET fuel fabrication. The intention of the talk is to provide the brief history and tie in an overview of current programs and investigations as related to NTP based W-UO2 CERMET fuel fabrication, and hopefully peak interest in advanced fuel fabrication technologies.
报告类型：	科技报告