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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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
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.
V. K. Sikka, J. Moteff
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 52-65
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16274
Articles are hosted by Taylor and Francis Online.
The thermal stability of neutron-induced defects in molybdenum irradiated in Experimental Breeder Reactor II (EBR-II) to a fast-neutron fluence of ∼1 × 1022 n/cm2 (E >1 MeV) clearly suggests that there are critical temperature regimes that should be avoided by reactor design engineers. These regions are manifested by a rapid change in the micro structure within a small temperature interval, a circumstance that can significantly influence the strength and corresponding ductility of the material. One critical temperature occurs at ∼800°C, where the irradiation-induced modulus-corrected strength could vary significantly compared to unirradiated molybdenum for a small temperature variation around 800°C. Voids have been shown to occur in specimens irradiated at 430, 580, 700, 800, 900, and 1000°C; these voids are stable at temperatures up to ∼0.60 Tm , rather than the 0.55 Tm value reported earlier for low fluence irradiations. The increase in the complete void removal temperature is suggested to exist due to the presence of a larger void size and the ordered void lattice structure in EBR-II samples.