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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.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
B. B. Chu, M. Mazumdar
Nuclear Science and Engineering | Volume 52 | Number 3 | November 1973 | Pages 396-398
Technical Note | doi.org/10.13182/NSE73-A19485
Articles are hosted by Taylor and Francis Online.
The method of correlated temperatures provided a technique for computing the hot channel factor when a maximum fixed, but nonzero, number of hot channels is permitted in a reactor core. This method made adequate allowance for the fact that, of the various identifiable uncertainties affecting the core, some are global and some are local in nature. In this Note, a method is provided which has the same objectives as those of the method of correlated temperatures and uses the same formulation, but does away with the Monte Carlo computations of the latter. It is believed that the analytical method provided in this Note can be more easily adapted to the computations of hot channel reliability in an actual reactor.