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NRC proposed rule for licensing reactors authorized by DOE, DOD
Nuclear reactor designs approved by the Department of Energy or Department of Defense could get streamlined pathways through the Nuclear Regulatory Commission’s commercial licensing process should applicants wish to push the technology into the civilian sector.
A proposed rule introduced April 2 by the NRC would “improve NRC licensing review efficiency, where applicable, by explicitly establishing by regulation an additional means for reactor applicants to demonstrate the safety functions of their reactor designs, and thus, would contribute to the safe and secure use and deployment of civilian nuclear energy technologies.”
D.K. Sze, P.A. Finn, J. Anderson, J. Bartlit, R. Sherman
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1601-1606
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29570
Articles are hosted by Taylor and Francis Online.
During the ITER design phase, the conceptual design of the fuel processing cycle has been established. The fuel processing cycle is designed to be able to handle all the tritium containing streams of the ITER. These streams include plasma exhaust, blanket tritium recovery, pellet propellent, neutron beam exhaust, water coolant detritiation, waste water from the room air detritiation system. The design is very conservative, i.e., the flow rate of each stream is high and the detritiation factor required is very high. A preliminary optimization study has been carried out to simplify the ITER fuel cycle design. We investigated: 1. The throughput and composition of the input tritium containing streams from various components to the fuelprocessing cycle. 2. The fraction of those streams needed to be detritiated. 3. The required detritiation factors required for each of the streams. The results of the investigation determined that the major input tritium containing streams can be reduced by at least a factor of 10. The required detritiation factor can be reduced from a factor of 100 to 106. The size of the fuel processing cycle, the tritium inventory and the complexity of this system can, therefore, also be reduced.