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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.
M. D. Freshley
Nuclear Technology | Volume 18 | Number 2 | May 1973 | Pages 141-170
Technical Paper | A Review of Plutonium Utilization in Thermal Reactors / Reactor | doi.org/10.13182/NT73-A31284
Articles are hosted by Taylor and Francis Online.
Irradiation performance data available to date indicate that the behavior of Zircaloy-clad thermal reactor mixed-oxide fuels is entirely satisfactory. There do not appear to be any inherent performance limitations created by the addition of small amounts of PuO2 to UO2. The wide range of test conditions include peak linear heat ratings sufficient to cause fuel melting and peak burnups to over 50 000 MWd/MTM. Because small PuO2 additions to UO2 have an insignificant effect on those fuel properties which could affect irradiation behavior, thermal reactor mixed-oxide fuel performs similarly and equally as well as UO2-only fuel. The evidence indicates that the PuO2-rich regions that persist in nonrestructured mechanically mixed, mixed-oxide fuel have an insignificant effect on performance. The extent of plutonium migration which can occur during irradiation also has an insignificant effect on mixed-oxide fuel behavior. Satisfactory defect behavior of Zircaloy-clad UO2-PuO2 fuel under normal operating conditions is indicated. Transient behavior can be affected by the presence of abnormally large PuO2 particles in mixed-oxide fuel; however, the effect appears to be of little practical significance. PuO2 additions to UO2 do introduce special considerations related to fuel design and fabrication. However, the successful development of a sound base technology assures the timely utilization of plutonium in water-cooled power reactors on a reload basis beginning in the mid-1970s.