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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
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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
W. J. Lindsey, P. L. Roggenkamp, W. K. Woods
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 78-82
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31069
Articles are hosted by Taylor and Francis Online.
Small-scale test irradiations of 237Np in the Richland and Savannah River production reactors have provided substantial empirical information on the mechanisms for formation of 236Pu. Application of this information to the design of larger scale irradiations in the Savannah River high flux reactor has resulted in successful production of 2 kg of 238Pu, meeting current isotopic specifications for the heart program. Further work is planned to develop practical technology of producing still larger amounts. The optimum location for target 237Np in the D2O reflector of the high flux charge has been established. Tests have demonstrated that matrix material for the targets is an important variable, and that the use of aluminum should be avoided. Irradiations of kilogram quantities of 241 Am have been completed and most of the resulting 242Cm will be allowed to decay into 238Pu before chemical processing (about two years). However, small amounts of the irradiated 241Am will be processed promptly to provide 242Cm for decay into ultra-high purity 238Pu.