Evaluation of Fluid Conduction and Mixing within a Subassembly of the Actinide Burner Test Reactor [electronic resource].
- Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 2007.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Additional Creators:
- Idaho National Laboratory
United States. Office of the Assistant Secretary for Nuclear Energy
United States. Department of Energy. Office of Scientific and Technical Information
- The RELAP5-3D code is being considered as a thermal-hydraulic system code to support the development of the sodium-cooled Actinide Burner Test Reactor as part of the Global Nuclear Energy Partnership. An evaluation was performed to determine whether the control system could be used to simulate the effects of non-convective mechanisms of heat transport in the fluid, including axial and radial heat conduction and subchannel mixing, that are not currently represented with internal code models. The evaluation also determined the relative importance of axial and radial heat conduction and fluid mixing on peak cladding temperature for a wide range of steady conditions and during a representative loss-of-flow transient. The evaluation was performed using a RELAP5-3D model of a subassembly in the Experimental Breeder Reactor-II, which was used as a surrogate for the Actinide Burner Test Reactor.
- Published through SciTech Connect.
Cliff B. Davis.
- Funding Information:
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