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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.
Chung-Yi Wang
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 332-348
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32571
Articles are hosted by Taylor and Francis Online.
An implicit finite difference method has been developed and incorporated into the ICECO code for analyzing hydrodynamics in the above-core region induced by the upper internal structure, and sodium spillage through penetrations and ruptured seals resulting from slug impact on the reactor cover. Eulerian description is employed so that flow through coolant passageways, large material distortions, two-dimensional sliding interfaces, flow around corners, and out-flow boundary conditions can be easily treated. In the analysis, the upper internals and the reactor cover are considered as perforated structures. A control-volume technique is utilized for deriving equations for the conservation of mass, momentum, and energy. The basic idea is to use actual fluid volume and actual flow areas in the mathematical formulation. Several modified Poisson equations are obtained, which govern the hydrodynamic pressures in the vicinity of the perforated structures. Sample problems are provided to illustrate the code capabilities in assessing the effect of the upper internal structure on the containment response and in estimating the amount of coolant ejected from the primary containment.