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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
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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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.
C. Lepscky, G. M. Testa, H. Hougaard, K. W. Jones
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 367-395
Technical Paper | Fuel | doi.org/10.13182/NT72-A31203
Articles are hosted by Taylor and Francis Online.
Two instrumented fuel assemblies, containing Zircaloy-clad UO2 fuel, namely IF A-132 (pellet, 95% TD, 10.0 wt% 235U) and IFA-133 (vibrocompacted powder, 85% TD, 10.0 wt% 235U) were irradiated in the Halden Boiling Water Reactor (HBWR) in Norway, in order to investigate the performance of fuel pins under central melting conditions; the maximum linear heat generation rate (LHGR) was about 1400 W/cm and the final burnup was 11 000 MWd/MTU. The initial molten zone covered about 35 and 65% of the fuel radius for the pelleted and vibrocompacted fuel, respectively. By means of the in-pile instrumentation, the dimensional changes vs generated power were recorded during irradiation. Furthermore through extensive postirradiation examinations the in-pile behavior of fuel and cladding was evaluated. In spite of incipient burnout condition, contact of molten or plastic fuel with the cladding, and localized overheating up to 900°C, the overall behavior gave no indication that irradiation to a higher burnup could not proceed satisfactorily. On the basis of this experiment it seems justified to assume that central fuel melting should not be considered as a primary constraint in the fuel design criteria.