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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.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
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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Latest News
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.
Jae-Woo Ju, Sang-Moon Lee, Kwang-Yong Kim
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 274-281
Technical Paper | Fission Reactors/Thermal Hydraulics | doi.org/10.13182/NT13-A15783
Articles are hosted by Taylor and Francis Online.
The outlet plenum of a pebble bed modular-type gas-cooled nuclear reactor was optimized using three-dimensional Reynolds-averaged Navier-Stokes analysis and optimization techniques. A shear stress transport turbulence model was used as a turbulence closure. Two design variables for the optimization were selected: dimensionless displacement on the horizontal line and the angle of rotation about the center of gravity of the roof support block. The objective function was defined as a pressure drop between the inlet and the outlet of the outlet plenum. Latin hypercube sampling was used for selecting experimental design points within the design space. The objective function value was obtained at each design point through numerical analysis. The results show that the optimal design significantly improved the performance of the outlet plenum with respect to pressure drop. Through optimization, the pressure drop decreased by 11.8% compared to the pressure drop under the reference geometry.