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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
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!
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Latest News
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.
R. T. Santoro, V. C. Baker, J. M. Barnes
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 274-295
Technical paper | Reactor | doi.org/10.13182/NT78-A31995
Articles are hosted by Taylor and Francis Online.
One-dimensional neutronic and photonic calculations have been carried out using the discrete-ordinates code ANISN to compare the nuclear performance of blanket and shield designs proposed for use in the Tokamak Experimental Power Reactor. The radiation transport was accomplished using cross-section data from the DLC-37 library (ENDF/B-IV). Nuclear heating and radiation damage rates were estimated using the latest available nuclear response functions. The nuclear analysis was performed for both nonbreeding and tritium-breeding blanket modules to compare the spatial variations of the radiation flux and energy distributions, nuclear heating, radiation damage, and tritium breeding. The nonbreeding blanket modules that utilize potassium plus Type 316 stainless steel or potassium only as the neutron and gamma-ray energy absorbing medium, and breeding blanket modules that use natural lithium as the fertile material were also evaluated as a function of the first wall cooling scheme.