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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
From South Korea to Belgium: Testing a high-density research reactor fuel
The Korea Atomic Energy Research Institute has developed a high-density uranium silicide fuel designed to replace high-enriched uranium in research reactors. Recent irradiation tests appear to be successful, KAERI reports, which means the fuel could be commercialized to continue a key global nuclear nonproliferation effort—converting research reactors to run on low-enriched uranium fuel.
E. Royer, E. Raimond, D. Caruge
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 154-165
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3381
Articles are hosted by Taylor and Francis Online.
The Organization for Economic Cooperation and Development/Nuclear Energy Agency Main Steam Line Break (MSLB) benchmark provides a comparison of state-of-the-art and best-estimate models used to compute reactivity accidents. A comprehensive study has been carried out by Commissariat à l'Energie Atomique and Institut de Radioprotection et de Sûreté Nucléaire with the CATHARE, CRONOS2, and FLICA4 codes. The effect of mixing between primary loops in the core vessel is analyzed, then zero-dimensional and three-dimensional (3-D) kinetics are compared, and finally, the effect of the core thermal-hydraulic model is presented. The aim of this analysis is to assess the 3-D effects in the MSLB accident and to explain the return-to-power occurrence.