Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly

التفاصيل البيبلوغرافية
العنوان: Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly
المؤلفون: Jan Vierendeels, V.R. Gopala, H. Doolaard, Elia Merzari, K. Van Tichelen, S. Keijers, Ferry Roelofs, Paul Fischer, J. De Ridder, Haomin Yuan, Joris Degroote
المصدر: NUCLEAR ENGINEERING AND DESIGN
بيانات النشر: Elsevier BV, 2016.
سنة النشر: 2016
مصطلحات موضوعية: Nuclear and High Energy Physics, Engineering, Technology and Engineering, 020209 energy, Nuclear engineering, Mechanical engineering, 02 engineering and technology, Computational fluid dynamics, 7. Clean energy, 01 natural sciences, 010305 fluids & plasmas, Thermal hydraulics, Benchmark (surveying), 0103 physical sciences, 0202 electrical engineering, electronic engineering, information engineering, General Materials Science, Research reactor, Safety, Risk, Reliability and Quality, Waste Management and Disposal, business.industry, Mechanical Engineering, Fluid mechanics, Nuclear Energy and Engineering, Nuclear reactor core, business, Energy source, Verification and validation
الوصف: As part of a U.S. Department of Energy International Nuclear Energy Research Initiative (I-NERI), Argonne National Laboratory (Argonne) is collaborating with the Dutch Nuclear Research and consultancy Group (NRG), the Belgian Nuclear Research Centre (SCK·CEN), and Ghent University (UGent) in Belgium to perform and compare a series of fuel-pin-bundle calculations representative of a fast reactor core. A wire-wrapped fuel bundle is a complex configuration for which little data is available for verification and validation of new simulation tools. UGent and NRG performed their simulations with commercially available computational fluid dynamics (CFD) codes. The high-fidelity Argonne large-eddy simulations were performed with Nek5000, used for CFD in the Simulation-based High-efficiency Advanced Reactor Prototyping (SHARP) suite. SHARP is a versatile tool that is being developed to model the core of a wide variety of reactor types under various scenarios. It is intended both to serve as a surrogate for physical experiments and to provide insight into experimental results. Comparison of the results obtained by the different participants with the reference Nek5000 results shows good agreement, especially for the cross-flow data. The comparison also helps highlight issues with current modeling approaches. The results of the study will be valuable in the design and licensing process of MYRRHA, a flexible fast research reactor under design at SCK·CEN that features wire-wrapped fuel bundles cooled by lead-bismuth eutectic.
وصف الملف: application/pdf
تدمد: 0029-5493
URL الوصول: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b7876a947ecb42f93da56c37b0906d4b
https://doi.org/10.1016/j.nucengdes.2015.11.002
حقوق: OPEN
رقم الأكسشن: edsair.doi.dedup.....b7876a947ecb42f93da56c37b0906d4b
قاعدة البيانات: OpenAIRE