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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
P. L. Viollet, J. P. Benque, J. Goussebaile
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 350-372
Technical Paper | doi.org/10.13182/NSE83-A15456
Articles are hosted by Taylor and Francis Online.
Finite difference numerical methods are available for the computation of unsteady non-isothermal flows with possibly strong buoyancy effects or head loss terms. The algorithm uses either velocity-pressure or velocity-stream-function formulations. The treatment of advective terms involves the method of characteristics. Arbitrary non-orthogonal curvilinear grids may be used, and turbulence is modeled by means of a k-ϵ eddy viscosity model. Two examples of application to liquid-metal fast breeder reactor thermal analysis are: 1. hot plenum flow in a pool-type vessel during flow and thermal transients, 2. unsteady flow in a pipe resulting from an inlet temperature change with a very low flow rate. For both cases, comparisons with experimental studies and applications to real reactors are shown.