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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.
Meeting Spotlight
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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Oct 2024
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Nuclear Science and Engineering
November 2024
Nuclear Technology
Fusion Science and Technology
Latest News
The DOE picks six HALEU deconverters. What have we learned?
The Department of Energy announced contracts yesterday for six companies to perform high-assay low-enriched uranium (HALEU) deconversion and to transform enriched uranium hexafluoride (UF6) to other chemical forms, including metal or oxide, for storage before it is fabricated into fuel for advanced reactors. It amounts to a first round of contracting. “These contracts will allow selected companies to bid on work for deconversion services,” according to the DOE’s announcement, “creating strong competition and allowing DOE to select the best fit for future work.”
Manuela Profir, Vincent Moreau
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 565-578
Research Article | doi.org/10.1080/00295450.2023.2175589
Articles are hosted by Taylor and Francis Online.
The pool-type experimental facility CIRColazione Eutettico (CIRCE) has been built by ENEA in support to the development of liquid-metal fast reactors. A computational fluid dynamics (CFD) model of the new test section, called the Thermal-hydraulic HElical Tubes Innovative System or THETIS, is being built, and is described along with the pretest numerical results. The pretest study analysis supports the dimensioning of the experimental setup and provides a sound but still not complete basis for the experimental transients. Appropriate thermal boundary conditions for the steady state are implemented. These conditions are found to be not suitable for thermal transients, hence the necessary compliance is analyzed and defined, requiring additional preliminary experimental tests. The main novelty in the refurbishment of the CIRCE is the installation of an innovative helical coil steam generator (HCSG). The realization of its numerical counterpart is challenging; therefore, a specific CFD model of the HCSG has been developed separately from the global model. Its preliminary results are described and discussed.