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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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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
R. H. Chen, M. L. Corradini, G. H. Su, S. Z. Qiu
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 46-59
Technical Paper | doi.org/10.13182/NSE12-22
Articles are hosted by Taylor and Francis Online.
In the present study, we propose a new fragmentation criterion for the explosion phase to take account of the effect of partial fuel melt solidification on the rapid fragmentation process. This new criterion judges whether or not the explosive fragmentation can occur by comparing the impact stress induced by vapor film collapse and water jet impingement with the fracture toughness of the corium crust layer. The fragmentation criterion was incorporated into the revised Thermal EXplosion Analysis Simulation (TEXAS) fuel-coolant-interaction (FCI) model TEXAS-VI and combined with the previously proposed fuel particle solidification model and the fragmentation criterion for the mixing phase. TEXAS-VI was compared to KROTOS alumina test K-44 and corium tests K-52 and K-53, and good agreement was obtained. The simulation results indicate that TEXAS-VI has the capability to consider the effect of partial solidification for both the mixing and the explosion phases of the FCI process and can capture the effect of fuel solidification, which reduces corium-water explosion energetics. Experiments K-52 and K-53 also demonstrate the ability of TEXAS-VI to model the effects of ambient pressure on energetics.