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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.
Hermann J. Möckel, Rainer H. Köster
Nuclear Technology | Volume 59 | Number 3 | December 1982 | Pages 494-497
Technical Paper | The Backfill as an Engineered Barrier for Radioactive Waste Management / Radioactive Waste Management | doi.org/10.13182/NT82-A33007
Articles are hosted by Taylor and Francis Online.
Portland cement stone samples simulating solidified active waste were 60Co-gamma-irradiated with doses up to 108 rad. The radiolytically produced gases were determined using a gas chromatographic technique. Various additives chemically comparable to actual low- and intermediate-level wastes were incorporated in the cement mixtures. Also the influence of the presence of oxygen during the irradiation was investigated. In no case could or NOx (from the decomposition of nitrate) be detected. In nitrate-free samples, only H2 is produced. The H2 yield ranges between 3 and 8 ml of H2 per kilogram of cement stone and per megarad radiation applied. It depends on the water content and the aging time of the samples; an influence of the concrete fluidizer content was not observed. The presence of nitrate in the samples gives rise to the production of O2 besides H2 and an overall decrease of the gas yield.