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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.
Joel McDuffee, Rich Christensen, Daniel Eichel, Mike Simpson, Supathorn Phongikaroon, Xiaodong Sun, John Baird, Adam Burak, Shay Chapel, Joonhyung Choi, Jacob Gorton, D. Ethan Hamilton, Dimitris Killinger, Sam Miller, Jason Palmer, Christian Petrie, Daniel Sweeney, Adrian Schrell, James Vollmer
Nuclear Science and Engineering | Volume 196 | Number 1 | October 2022 | Pages S234-S259
Technical Paper | doi.org/10.1080/00295639.2021.2017663
Articles are hosted by Taylor and Francis Online.
The mission of the Versatile Test Reactor (VTR) is to enable accelerated testing of advanced reactor fuels and materials as required for advanced reactor technologies. Each advanced reactor type has unique challenges, and these challenges affect the design of the testing vehicles used for accelerated testing. For molten salt reactor testing, some of the key focus areas are (1) understanding the complex thermal-hydraulic systems and materials that will facilitate heat removal from the reactor core, (2) mitigating the corrosion-associated issues that arise from using these materials at high temperatures, and (3) understanding how to measure and control salt composition/chemistry and properties during irradiation. This paper details the progress made toward surmounting these challenges to support future molten salt cartridge experiments in the VTR. Broadly, this work involves two major thrusts: design and analysis of an operating cartridge loop, and development of the instrumentation and control system needed to operate the loop successfully.