ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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August 2024
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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.
J. T. A. Roberts, B. J. Wrona, D. Fischer, J. A. Buzzell
Nuclear Technology | Volume 27 | Number 2 | October 1975 | Pages 267-272
Technical Paper | Fuel | doi.org/10.13182/NT75-A24294
Articles are hosted by Taylor and Francis Online.
Modifications to the direct electrical heating apparatus have enabled it to be used successfully to heat irradiated mixed-oxide fuel pellets to melting in an α-γ hot cell. For this purpose, a fuel extrusion device was constructed to remove irradiated fuel from its cladding. Proof-testing was successfully conducted using two UO2-20 wt% PuO2 pellets irradiated in the Experimental Breeder Reactor II to 3.25 at.% burnup at ∼ 3.05 kW/m (∼10 kW/ft). The sequence of events leading to fuel failure—namely, melting, swelling, and fragmentation—agree with observations from inreactor accident simulations.
