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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Carles De Las Cuevas, Lourdes Miralles, Juan José Pueyo
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 325-336
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35237
Articles are hosted by Taylor and Francis Online.
Laboratory irradiations at a constant dose rate of 15 kGy/h at 100°C have enabled the study of the radiation damage in several types of rock salt. Total doses ranged from 20 kGy to 48.9 MGy. Two methods (optical absorption and release of hydrogen by reaction with water) have been used to measure the concentration of radiation-induced defects. Their concentration was compared with the dose and the chemical and mineral composition of rock salt samples, using multivariate statistical techniques. The results show a loglinear increase in the concentration of colloidal sodium with dose, whereas the F-centers concentration remains nearly constant. Moreover, there is a clear influence of the mineral composition of the rock salt in the radiation damage, leading to defect concentrations varying over one order of magnitude for the same dose. Rock salt with small amounts of accessory minerals presents the lowest defect concentration. Experimental data have been compared with the theoretical predictions obtained by the Jain-Lidiard model. For doses higher than 1 MGy, both values are of the same order of magnitude.