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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Har Swroop Sharma, Nandakumar B. Khedekar, Surendranath G. Marathe, Hem Chand Jain
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 399-405
Technical Paper | Technique | doi.org/10.13182/NT90-A34378
Articles are hosted by Taylor and Francis Online.
Controlled potential coulometric studies are carried out for the determination of plutonium in mixed (U, Pu) carbide fuel samples. Variations in coulometric blank and interference due to iron and organic impurities are investigated. These impurities are likely to come from the sample, reagent acids, and during dissolution of carbide samples. A method for the determination of plutonium involving the successive addition of sample solution aliquots directly into the coulometric cell is evolved and demonstrated. Employing this method, eight to ten aliquots, each containing 2 to 5 mg of plutonium, can be analyzed in the same electrolyte (25 ml 1 N H2SO4), thus gaining an appreciable reduction in the analysis time. Also, the volume of analytical waste is considerably reduced. Precision and accuracy within 0.2% are achieved in the routine analysis of fuel samples.