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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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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.”
Kazuya Ohgama, Taira Hazama, Hiroki Katagiri, Atsushi Takegoshi, Tetsuya Mouri
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1336-1353
Research Article | doi.org/10.1080/00295450.2023.2295168
Articles are hosted by Taylor and Francis Online.
In the prototype fast breeder reactor Monju, reaction rate distributions of the fission reaction rates of 239Pu, 235U, and 238U and the capture reaction rate of 238U were measured using activation foils during its system startup test. The measurements in the core and radial blanket regions were evaluated in detail, and their reliability and usefulness as the validation data for fast reactor neutronics design methodologies were examined through a comparison with calculations. The reaction rate data measured in Monju were confirmed all reliable and useful as the validation data. The fission reactions of 239Pu, 235U, and 238U can be validated with an accuracy of a few percent in the core and blanket regions. The capture reaction of 238U in the core region also can be validated with a similar accuracy, whereas a precise calculation of the foil cross section is necessary to consider the resonance shielding effects of the surrounding fuel pins and a foil.