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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.
Esko H. Tusa, Asko Paavola, Risto Harjula, Jukka Lehto
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 279-284
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35008
Articles are hosted by Taylor and Francis Online.
At the Loviisa Nuclear Power Station (NPS) all liquid waste, i.e., spent resins and evaporator concentrates, have been stored in a large tank storage facility. Dominating radionuclides in the evaporator concentrates have been 134Cs and 137Cs. By removing cesium from the waste, purified liquid can be released within licensed release limits, and cobalt as a second dominating nuclide is left in a small waste volume on the bottom of the tank. Since 1985, the use of inorganic hexacyanoferrate-based materials for purification of cesium has been studied. A full-scale system for cesium removal, called the IVO-CsTreat System, was constructed in 1990 to 1991. A method to produce the ion exchanger in granular form in industrial scale was developed, and the facility to produce it was constructed. The ion exchange material was produced in 1991, and the full-scale purification facility was commissioned at the Loviisa NPS in October 1991. In the test run, 253 m3 of concentrate was purified between October 31, 1991 and June 11, 1992 with three ion exchange columns, each with a volume of 8 ℓ. A volume reduction factor of over 10000 was achieved as the ratio of liquid and ion exchanger volume. The decontamination factor for cesium was ∼2000.