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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Latest News
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
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.
