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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.
Jeffrey W. Ray, Albert B. Reynolds
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 394-403
Technical Paper | Material | doi.org/10.13182/NT90-A34460
Articles are hosted by Taylor and Francis Online.
The effect of various antioxidants and antioxidant concentrations on the room-temperature radiation stability of ethylene propylene diene monomer (EPDM) and cross-linked polyethylene (XLPE) materials used as insulation for electric cable in nuclear power plants is measured. Relative elongation to rupture between aged and unaged material is used as the measure of stability. The materials are irradiated to doses up to 2.0 MGy (200 Mrad) at a dose rate of 300 Gy/h (3 x 104 rad/h) in the Cobalt-60 Gamma Irradiation Facility at the University of Virginia. Several of the antioxidants in EPDM perform well to the maximum doses for which reliable data were obtained of either 1.0 or 1.6 MGy. An XLPE material with Agerite™ MA antioxidant performs well to the maximum dose for which reliable data were obtained of 1.0 MGy. Stabilization at 1.0 MGy increases with increasing antioxidant concentration, though not in proportion to the concentration.