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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.
Erik Kolstad
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 481-491
Technical Paper | Material | doi.org/10.13182/NT80-A17696
Articles are hosted by Taylor and Francis Online.
A presentation is provided of the design features and measuring capabilities of a high pressure test rig used for study of mechanical aspects of fuel performance under simulated pressurized water reactor conditions. In-pile profilometry data on one small gap (55 μm) segment (SGS) and one large gap (170 μm) segment (LGS) show different trends with increasing burnup to 5.4 MWd/kg UO2 (end of test). Significant fuel-induced cladding deformations developed in the SGS during the startup ramp, including clear permanent circumferential ridge formations. During subsequent irradiation, only minor permanent dimensional changes were measured. The deformation behavior of the LGS was characterized by a reduction in the cladding average diameter and an increase in ovality with burnup (time). The highest rate of change for both quantities was observed at low burnup. A brief review of ten current Zircaloy creep correlations reveals a large spread in predictive capabilities.