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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Bipartisan nuclear waste bill introduced in U.S. House
U.S. representatives Mike Levin (D., Calif.) and August Pfluger (R., Texas) have introduced the bipartisan Nuclear Waste Administration Act of 2024, which would establish an independent agency to manage the country’s nuclear waste.
In addition to establishing a new, single-purpose administration to manage the back end of the nuclear fuel cycle, the bill would direct a consent-based siting process for nuclear waste facilities and ensure reliable funding for managing nuclear waste by providing access to the Nuclear Waste Fund. According to Pfluger and Levin, the bill’s provisions are in line with recommendations from the Blue Ribbon Commission on America’s Nuclear Future.
Akihiko Inoue
Nuclear Technology | Volume 90 | Number 2 | May 1990 | Pages 186-190
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34413
Articles are hosted by Taylor and Francis Online.
A method for reprocessing uranium and plutonium mixed-oxide fuel, including uranium dioxide fuel, is presented. The method is based on the oxidation process of the fuel and the dissolution of pulverized fuels (U3O8 and PuO2) in nitric acid. To dissolve Pu02, a uranous nitrate solution prepared from uranyl nitrate by electrolytic reduction is utilized. This reprocessing method has an economic advantage over the conventional Purex process because it does not use an expensive solvent extraction process to separate uranium, plutonium, and fission products. The cost of the process is estimated to be 80% that of the Purex process, and the cost of refabrication does not change greatly because remote operation is not needed. This process also has an advantage over the Purex process from the viewpoint of the diversion resistance of nuclear material because pure plutonium cannot be recovered in the process.
