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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
N. Kaffezakis, D. Kotlyar
Nuclear Technology | Volume 206 | Number 1 | January 2020 | Pages 48-72
Technical Paper | doi.org/10.1080/00295450.2019.1616475
Articles are hosted by Taylor and Francis Online.
This paper details the development and optimization of a novel seed blanket fuel assembly designed for utilizing high-conversion Th-233U fuel cycles in the current fleet of pressurized water reactor vessels. Previous studies have revealed the necessity to downrate the total power of cores loaded with seed blanket assemblies due to issues with high power density in the seed regions and thermal-hydraulic failure. This new design features solid packing of the blanket region with the objective of increasing the total power and the economic competitiveness. This paper utilized the Serpent code to study the depletion of various designs of the solid blanket assembly, and THERMO is utilized for thermal-hydraulic analysis. A favorable design was developed that attained an excess 1.7% fissile material from the initial loading and that can be run at a maximum power up to 66% greater than the comparable designs used as references in this paper.