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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.
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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
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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 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.
S. Sharafat, C. P. C. Wong, E. E. Reis, THE ARIES TEAM
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 901-907
Advanced Reactor | doi.org/10.13182/FST91-A29459
Articles are hosted by Taylor and Francis Online.
The ARIES-I reactor is a 1000-MWe, DT-burning tokamak reactor that combines present-day physics with advanced engineering technology such as high-field superconducting magnets and low-activation SiC composites as structural material. Recent developments in the manufacturing of fiber-reinforced ceramics for improved mechanical properties make these materials promising candidates for future fusion reactors. The low-activation, low-afterheat characteristics of SiC can lead to an inherently safe reactor design with a Class-C waste-disposal rating. The first wall, blanket, shield, and the divertor all use SiC composite as structural material and helium as coolant. The thermomechanical behavior of the first wall is analyzed using the ANSYS finite-element code. The analysis shows that the first wall performs well below suggested allowable stress and temperature limits. Although the finite element analysis assumes idealized conditions, the results indicate that SiC composite materials could perform well under specified operating conditions. Given the potential safety and environmental advantages of SiC composites, the current large-scale developmental efforts taking place outside of the fusion community should be complemented by R&D efforts that focus on neutron- and ionizing-irradiation effects on SiC composite materials.