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Division Spotlight
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.
Han Y. Chu
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 363-377
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32573
Articles are hosted by Taylor and Francis Online.
An arbitrary Lagrangian-Eulerian method used to describe the fluid motion together with a Lagrangian method used to analyze the structural response for solving fluid-structure interaction problems are presented. A two-dimensional computer code, ALICE, based on these methods is developed for analyzing transient phenomena generated in a reactor-containment system during a hypothetical core disruptive accident. The finite difference equations that are used to approximate the governing equations for the motion of the fluid can be solved with either an explicit or implicit scheme; the finite element equations that are used to approximate the governing equations for the structure can be performed only in the explicit scheme. Thus, the ALICE code can perform two types of coupling calculations for the fluid and structure (explicit-explicit and implicit-explicit). The arbitrary Lagrangian-Eulerian method used to describe the fluid motion allows the vertices of the fluid computing mesh to