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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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
James M. Broughton, Pui Kuan, David A. Petti, and, E. L. Tolman
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 34-53
Plenary Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27637
Articles are hosted by Taylor and Francis Online.
The primary objective of the U.S. Department of Energy Three Mile Island Unit 2 (TMI-2) research program, conducted by the EG&G Idaho TMI-2 Accident Evaluation Program, is to develop a comprehensive and consistent understanding of the TMI-2 accident. The accident scenario developed from this research is presented, including information relative to (a) the progression of core damage leading to a consolidated region of partially molten core material, (b) continued heatup of this consolidated region leading to extensive melting of the core, (c) failure of the supporting crust encasing the molten core material and relocation of 15 to 20 tonnes of molten core material into upper and lower core support assemblies and the lower plenum, and (d) interaction of molten core material with coolant and support structures in the lower plenum. Fission product release from fuel during the accident is also discussed.
