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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.
Valerii Palkin, Eugene Maslyukov
Nuclear Science and Engineering | Volume 196 | Number 9 | September 2022 | Pages 1091-1100
Technical Paper | doi.org/10.1080/00295639.2022.2045146
Articles are hosted by Taylor and Francis Online.
The paper offers a double-cascade scheme for reducing the concentration of 232, 234, 236U isotopes in reprocessed uranium hexafluoride. The greatest decrease of the ratio between the masses of 236U and 235U is provided in the product of the first ordinary cascade enriched by 235U at the concentration of less than 20%. For this purpose, a special mode of stages operation is determined. Enrichment by 232, 234U is performed in the second ordinary cascade, which is fed by the product of the first cascade. After being purified from 232, 234U, the waste flow is diluted till the concentration of 235U is less than 5%. This paper describes the methodology for calculating the parameters of cascades with the stage separation factors correlating with gas centrifuges. This methodology served as a basis for a computational experiment. It is demonstrated that the output gained after the dilution meets the requirements of the American Society for Testing and Materials C996-20 specification for the commercial grade of low-enriched uranium hexafluoride in terms of 232, 234U isotopes. The content of 236U in it is several times less than during the direct enrichment of reprocessed uranium hexafluoride.