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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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!
Latest Magazine Issues
Jun 2024
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Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
N. E. Stauff, L. Buiron, B. Fontaine, G. Rimpault
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 241-250
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A15781
Articles are hosted by Taylor and Francis Online.
Sodium-cooled fast reactors (SFRs) remain the favorite candidate in France for a Generation IV (Gen IV) reactor fleet to be deployed within this century. Compared with earlier generations (Phénix, Superphénix, and European fast reactor), Gen IV SFRs require attractive economics together with enhanced safety and nonproliferation criteria. An innovative approach named Mathematical Estimation of Transients for Reactor design Orientation (METRO) has been developed with the objective of taking into account both SFR core economic performance and SFR transient incident behavior at an early stage of the core design process. Loss-of-flow, loss-of-heat-sink, and overpower transients are evaluated. Simplified modeling of transients has been developed and benchmarked against reference calculations with satisfactory results. The METRO approach to assessing the efficiency of design orientations is described in the following and applied to a carbide-fueled reactor core.