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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
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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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.
S. R. Bierman, E. D. Clayton
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 131-144
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32730
Articles are hosted by Taylor and Francis Online.
A series of criticality experiments with 2.35 and 4.31 wt%o 235U-enriched UO2 rods in water was performed to provide well-defined benchmark-type data on thick steel reflecting walls. For each fuel enrichment, the critical separation between three subcritical fuel clusters was observed to increase as 178.5-mm-thick reflecting walls of reactor-grade steel was moved toward the fuel. This increase was observed for fuel clusters having an undermoderated water-to-fuel volume ratio of 1.6 and for fuel clusters having near optimum neutron moderation (2.92 for the 2.35 wt% 235U-enriched fuel and 3.88 for the 4.31 wt% 235Uenriched fuel). In all cases the critical separation between fuel clusters increased to a maximum as the steel walls were moved toward the fuel clusters. This maximum effect was observed with ∼10 mm of water between the fuel clusters and the steel reflecting walls. As this water gap was decreased, the critical separation between the fuel clusters also decreased slightly. Measurement data were also obtained for each enrichment with neutron absorber plates between the fuel clusters having the 1.6 water-to-fuel volume ratio. During these measurements, the steel reflecting walls were at the near optimum distance from the fuel clusters. The fixed neutron absorbers for which data were obtained include Type 304L stainless steel, borated Type 304L stainless steel, copper, copper containing 1 wt% cadmium, cadmium, and two tradename materials containing boron (Boral and Boroflex).