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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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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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Vladimír Balek, Miroslav Vobořil, Václav Baran
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 53-59
Technical Paper | Fuel | doi.org/10.13182/NT80-A17069
Articles are hosted by Taylor and Francis Online.
Emanation thermal analysis (ETA) is demonstrated as a tool for the objective characterization of solid phases arising during treatment of the uranyl gel microspheres up to the final UO2 product. The method is able to monitor very sensible differences in the morphology, surface area, and structure of a solid, as well as their changes when heated. The ETA results for seven samples are discussed and correlated with results from other independent methods (differential thermal analysis, thermogravimetry, thermodilatometry, and density measurements). Various preparation conditions of the internal gelation technique, such as uranium concentration, concentration of gelation additives, the way of leaching, etc., are reflected. The ETA is proposed as a method for simulating thermal processes of UO2 fuel preparation.