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A closer look at the initial NLIC selections—Part 2
In January, the Department of Energy announced its new Nuclear Lifecycle Innovation Campus (NLIC) program, inviting states via a request for information to express their interest in hosting a facility supporting work from the front to the back end of the nuclear fuel cycle.
By April, 26 states had expressed interest in hosting such a facility. At the end of July, the DOE signed memorandums of understanding with five states—Idaho, Louisiana, Oklahoma, Tennessee, and Utah—to more closely explore the possibilities of state-federal partnerships. These MOUs are not firm commitments from either the federal or state governments. Time will tell which—if any—of the five states develop projects through the program. In the meantime, today, we are taking a close look at what Utah, Idaho, Tennessee can offer in terms of a preexisting nuclear sector that could support new fuel cycle developments.
G. L. Kulcinski et al.
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 373-378
Alternate Concepts/Applications | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST12-576
Articles are hosted by Taylor and Francis Online.
The University of Wisconsin-Madison has conducted research on gridded inertial electrostatic confinement (IEC) devices for the past 18 years. There are currently 4 experimental devices operating at voltages up to 180 kV and 60 mA. These devices have uncovered several new phenomena that have greatly improved our understanding of IEC devices. Recent advances include the discovery of a significant negative ion component of DD plasmas and spatial profiles of fusion reactions that did not conform to our prior understanding of these devices. The use of this technology has also contributed to our understanding of surface damage to high temperature in-vessel W components after even low exposures to energetic He ion fluences. Expansion of the voltage-ion current parameter space to 300 kV-200 mA in the near future will help our understanding of advanced fusion fuel cycles.