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
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.
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.
M. D. Freshley, L. J. Harrison
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 177-191
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31144
Articles are hosted by Taylor and Francis Online.
The results of comparative transient tests performed in the Transient Reactor Test Facility (TREAT) indicate that the cladding failure threshold energy for nonirradiated vibrationally compacted and pellet-containing oxide fuel capsules is about 270 cal/g UO2. At this energy input, general cladding melting and rapid deterioration due to reaction with water vapor occur for both fuel types. In vipac fuel capsules the cladding was penetrated by the ejection of molten UO2 whereas in pellet-containing capsules the cladding rapidly deteriorated without the presence of molten fuel. When tested at near cladding failure threshold energies, the extent of metal-water reaction is comparable for the two fuel types.