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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.
E. E. Gruber
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 617-634
Technical Paper | Fuel | doi.org/10.13182/NT77-A31871
Articles are hosted by Taylor and Francis Online.
The need for a capability to predict transient fission gas behavior arises because of the complexity of fission gas response to transient conditions, the importance of fission gas to fuel mechanical response, and the prevalent limitations on experimental information relevant to the problem. A detailed mechanistic analysis of intragranular swelling and release of gas from grains to grain boundaries, both as they result from transient heating, has been developed and incorporated in a fission gas release and swelling code (FRAS). A generalized parametric model to approximate the results that would be obtained from the more detailed calculations has also been developed. The need for this model arises from the necessity to consider the fission gas effects in more general multinode accident-analysis and pin-mechanics codes. For such calculations, the FRAS code is prohibitive in its demands on computer storage and execution time, while the parametric FRAS (PFRAS) code reduces these demands by an order of magnitude. Transient calculations have been carried out with both codes, both to illustrate the sensitivity of the results to the parameters and to indicate the level of confidence that can reasonably be ascribed to PFRAS results. The parameters considered include initial gas concentration, grain size, heating rate, thermal gradient, and pressure. The PFRAS model gives a satisfactory approximation to FRAS results for the broad range of parameters surveyed.