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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.
John E. Mendel
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 72-87
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31739
Articles are hosted by Taylor and Francis Online.
Glass is a good material in which to incorporate high-level radioactive waste (HLW) for permanent storage. HLW, a complex mixture of fission products and actinides, results from the reprocessing of spent power reactor fuel elements to reclaim uranium and plutonium. Processes for making low-temperature waste glasses (1050°C processing temperature) have been developed to the stage that they can be utilized in commercial reprocessing plants in the early 1980’s. A representative low-melting waste glass formulation has been shown, in accelerated tests, to possess satisfactory thermal and radiation stability for many centuries of storage, and indications are that this stability will be maintained for longer times. The waste glass can be melted and stored in Type 304L stainless-steel canisters, although investigations of metals that may have increased high-temperature strength is continuing. A ceramic melting process that will permit manufacture of higher melting HLW glass, if this proves desirable, is also being developed.