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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Pekka Jauho, Risto Tarjanne
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 19-28
Technical Paper | Reactor | doi.org/10.13182/NT71-A30898
Articles are hosted by Taylor and Francis Online.
A calculation method developed for mixed-fuel lattices, consisting mainly of natural uranium rods and a small number of enriched rods isolated from each other, is studied with the aid of pulsed -neutron and exponential experiments. The experiments and theory are compared by means of the asymptotic spatial and time decay constants. In the theoretical calculations the natural uranium lattice is homogenized and the multigroup diffusion theory is applied; the enriched rods are described heterogeneously by using the monopole approximation. A separate transport theoretical cell calculation is carried out for the monopole boundary condition to obtain the relationship between the neutron current and flux at the surface of the lattice cell corresponding to an enriched rod. The results show that this kind of treatment is valid, although the cell calculation, where the axial flux dependence is disregarded, causes an error in the exponential experiments that is opposite to and greater than that in the pulsed-neutron experiments.