![]() The next generation of nuclear reactors and fuel cycle facilities must incorporate Safeguards, Security, and Safety by Design so that these facilities are intrinsically safe and secure now and into the future. In addition to developing tools for assessing reactor safety, security, and the safe storage of existing waste we also focus on the successful deployment of advanced reactors and other nuclear facilities. Our work informs decisions the United States government makes regarding nuclear reactor licensing, radioactive waste storage, transportation, safeguards, and disposal for current and future waste, impacting generations to come. The tools and research we develop at Sandia are critical to ensuring that nuclear reactors are safe and secure and that spent nuclear fuel and radioactive waste is safely and securely stored away from the environment and people. The objectives of Phase II are to provide a sodium turbulent flow and heat transfer database for CFD and subchannel model validation emphasize the importance of uncertainty analysis for TH simulations establish best practices for quantification of geometry modelling, input data, fluid properties, and other uncertainties associated with the complex flows in LMFR bundles develop guidance for CFD model/code validation for LMFR fuel bundles that can be used to improve the existing standards update the current TH models for pressure drop and inter-channel mixing and develop the hybrid experiment/simulation database necessary to establish and calibrate the low order models with high resolution (both experimental/numerical) data.Sandia provides science and engineering research for traditional light water reactor and new advanced reactor safety, security, spent nuclear fuel storage, transportation, security, safeguards, and disposal. ![]() ![]() Phase II: Numerical predictions of the Thermal Hydraulic Out of Reactor Safety (THORS) integral effect tests The objectives of Phase I are to provide a detailed geometry of the bundle test section and boundary conditions and a high-resolution experimental database of isothermal turbulent flow and pressure drop acquired from a 61-pin wire-wrapped hexagonal fuel bundle (all from TAMU) assess the performance of numerical schemes and turbulent models currently implemented in the state-of-the-art Computational Fluid Dynamics (CFD) codes and establish best practices for uncertainty quantification (UQ) of model geometry, initial and boundary conditions, and other associated uncertainties for CFD calculations. Phase I: Steady-state numerical predictions of Texas A&M University (TAMU) separate effect test Phase II: Numerical predictions of the Thermal Hydraulic Out of Reactor Safety (THORS) integral effect tests and comparison to experimental results.Įach phase will include several exercises and will be planned to accommodate as many numerical prediction methods as possible.Phase I: Steady-state numerical predictions of Texas A&M University (TAMU) separate effect test and comparison to experimental results.The LMFR T/H benchmark consists of two Phases: ![]() The benchmark is part of the Expert Group on Reactor Core Thermal-Hydraulics and Mechanics (EGTHM) activities. The work is supported by the US NRC (Grant 31310021M0009) and endorsed by the NEA. To establish best practise guidance for LMFR thermal hydraulics simulations and to compare different numerical appraoches on an international level, a benchmark was prepared jointly by North Carolina State University (NCSU) and Texas A&M University (TAMU), USA, in co-operation with the United States Nuclear Regulatory Commission (US NRC) and OECD Nuclear Energy Agency (NEA). The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs, and many numerical and experimental studies have been performed on LMFR core geometry.
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