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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
Kazys K. Almenas, Joseph M. Marchello
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 263-275
Technical Paper | Reactor | doi.org/10.13182/NT78-A32112
Articles are hosted by Taylor and Francis Online.
The effect of a mechanistic drop evaporation model on the pressure-temperature transient of a containment under loss-of-coolant accident (LOCA) conditions has been investigated. To implement the model, the traditional two-node lumped parameter (atmosphere and sump) had to be expanded to encompass additional open thermodynamic systems. The calculations were compared against results obtained by a widely employed containment analysis code using the instantaneous evaporation model. The mechanistic drop evaporation model was found to produce higher peak pressures and substantially higher degrees of superheat for a steam line break LOCA. The dependence of pressure in both saturated and superheated air-steam atmospheres was generalized in terms of normalized pressure-energy derivatives. For superheated atmospheres, these derivatives were found to depend on the mode of energy removal. Two idealized energy removal modes were defined (purely condensing and purely noncondensing). The normalized pressure-energy derivatives for these mechanisms were found to differ by a factor of 2 to 3 for the parameter range of interest to containment analysis.