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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.
P. A. Pizzica, H. H. Hummel
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 313-321
Nuclear Safety | doi.org/10.13182/NT82-A32860
Articles are hosted by Taylor and Francis Online.
Various loss-of-flow cases have been calculated for a commercial-sized liquid-metal fast breeder reactor. Particular attention has been paid to the development of loss-of-flow-driven transient-overpower (LOF-TOP) conditions. In such conditions, it is crucial to consider when an initial cladding breach might occur in LOF-TOP pins and over what length of time the initial cladding breach might extend in fuel pins failing under burst pressure. This study shows that the neutronic energy deposition in transient calculations including LOF-TOP pin failures can increase substantially compared to a calculation excluding such LOF-TOP failures in two ways. First, there will be an increase if there is no extension of an initial cladding failure in LOF-TOP pins or if there is a relatively long delay in the extension. Secondly, when, in applying a fuel melt fraction criterion for pin failure, the same melt fraction is specified for failure extension as for initial failure, which implies a certain delay time for failure extension, there will be an increase in the energy deposition compared to the case without any LOF-TOP failures only when the specified fuel melt fraction becomes very large. However, even in the case with the largest failure melt fraction, there will be no increase in energy deposition when a rapid enough failure extension is assumed. These calculations make a number of very conservative assumptions. The purpose of the study is not to provide a best estimate of accident conditions but to show how quickly an initial cladding breach must extend in such conservative calculations if it is to limit the increase in neutronic energy deposition.