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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.
L. C. Walters, J. H. Kittel
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 273-280
Technical Paper | Fuel | doi.org/10.13182/NT80-A32473
Articles are hosted by Taylor and Francis Online.
The reduction in projected sodium outlet temperatures for commercial liquid-metal fast breeder reactors has renewed the interest in metal fuels. The U-Pu-Zr or Th-Pu-U-Zr metal fuel pins, sodium bonded to stainless-steel claddings, will yield high burnup along with adequate fuel-cladding compatibility. High burnup capability is assured by designing the fuel element so that interconnected porosity and flssion-gas release occur prior to fuel-cladding contact. Interconnected porosity and fission-gas release take place at about 30% fuel-volume swelling, independent of the metal fuel composition. The U-Fs/Type 316 stainless-steel-clad driver-fuel element used in the Argonne National Laboratory Experimental Breeder Reactor II is designed to take advantage of the phenomenon of interconnected porosity, and burnups in excess of 10 at.% are typically achieved prior to cladding breach. The adequate fuel-cladding compatibility, high burnup potential, superior breeding performance, and demonstrated remote refabrication have made metal fuels an attractive alternative for fast reactor design.