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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
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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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.
Laila A. El-Guebaly
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 829-834
Neutronics and Shielding | doi.org/10.13182/FST83-A22963
Articles are hosted by Taylor and Francis Online.
Neutronics and photonics analysis for UWTOR-M was carried out to assess radiation streaming effects on reactor performance. The effect the lithium enrichment in the Li17Pb83 breeder has on radiation streaming was investigated. Using an enrichment of 35% was found to yield an adequate tritium breeding ratio of 1.08 and an overall energy multiplication of 1.153. The bulk shield was optimized to reduce the radiation effects in the superconducting magnets with the limited shielding space available in the design. Detailed analysis for the radiation streaming into the divertor regions has been performed. The divertor targets were found to recover 91% of the streaming energy.
