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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.”
C. Muirhead, H. Li, K. Pilatzke, M. Byers, R. Carson, H. Boniface, S. Suppiah
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 281-285
Technical Paper | doi.org/10.1080/15361055.2017.1290974
Articles are hosted by Taylor and Francis Online.
Canadian Nuclear Laboratories (CNL) is developing a Proton Exchange Membrane-based (PEM) electrolyser intended for tritium removal. Commercially available Nafion® N-1110 membranes have been exposed to tritiated water (with a β activity of about 37 GBq/mL) prepared in the Tritium Facility at CNL. Three equivalent batches of Nafion® N-1110 membranes (each with a dimension of 4 cm × 4 cm) were exposed to β-doses of 67 kGy, 155 kGy, and 255 kGy, respectively.
The exposed membranes required decontamination for characterization and testing. A few different decontamination methods have been experimentally studied. These methods can be categorized as water elution and chemical soaking. The measured tritium concentration in eluent decreased quickly in the first 30 days of water elution, followed by a slow decay afterwards until reaching a plateau after about 100 days. Chemical soaking proved to be more effective than the water elution method and high temperature facilitated the tritium release.