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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.
Young-Jin Kim, Sang-Tae Kim, Dong-Seok Im, Nam-Yong Jung, Yaung-Su Kim, Seong-Yeon Yoo
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 357-361
Safety, Environment, and Tritium Handling | 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/FST13-A18103
Articles are hosted by Taylor and Francis Online.
In the cooling water system (CWS), being infrastructure for large research facility, one of the important issues is the operation reliability, and then the minimizing of operation and maintenance costs. For optimum design, we studied the cooling loops for pulse and continuous operations of clients, volume and inside piping structure of storage tanks, two-step heat exchanger, safety devices and energy conservational operation of the CWS. During commissioning, the flow rate shortage due to increase of pump head by rise of client pressure drop was resolved as the operation of a stand by pump. The unexpected water pressure hunting occurred at an ion cyclotron ranges of frequency (ICRF) inlet port was stabilized by exchange of the starting system of motor and transfer of a constant flow rate valve from the water outlet port to the inlet port of the ICRF. We confirm that a polishing system, a first neutral beam injection cooling loop and a plasma facing component baking system can be stably operated in the upgrade step of clients. To improve the coefficient of performance and stability of operation in chiller, we will develop the new header, decreasing the gap of inlet temperature of cooling towers.