Benchmark CFD simulation of flow through a tube bundle with selected turbulence models
Creators
- 1. Mechanical and Nuclear Engineering, Kansas State Univ., Manhattan, KS (United States)
Description
Computational fluid dynamics (CFD) will increasingly be used as a tool in the design engineering of advanced nuclear systems, such as the Very High Temperature Reactor (VHTR). Codes such as STAR-CD, FLUENT and several others can facilitate evaluation of thermohydraulic performance of various sub-systems and regions of the reactor system. One such CFD application is of flow in the lower-plenum of the VHTR. However, as design certification is called upon by nuclear industry and regulatory authority, any first-of-a-kind application of CFD to plant design needs to undergo a formal validation and verification (V and V) procedure. Benchmarking a CFD code against a generally accepted dataset from an experiment with similar flow phenomena is an important step in V and V. In the present study, we sought to simulate flow over a tube bank (with tubes of one diameter), for which an accepted velocimetric database exists (Simonin and Barcouda). Using both STAR-CD and FLUENT independently, under steady and transient conditions, and with various turbulence models, we investigated the flow over a single and multiple tube bundle. Some initial results from the simulations and analyses thereof will be described. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [9 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39048657
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; F CODES; FLUID FLOW; FLUID MECHANICS; HEAT EXCHANGERS; MIXING; NAVIER-STOKES EQUATIONS; NUMERICAL ANALYSIS; S CODES; STRATIFICATION; TUBES; TURBULENCE; VALIDATION; VHTR REACTOR; VISCOSITY
- Descriptors DEC
- COMPUTER CODES; DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATHEMATICS; MECHANICS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; TESTING; THERMAL REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name Final Paper, PaperID ICONE15-10281.pdf; 17 refs., 9 figs., 1 tab.