Published 2013 | Version v1
Miscellaneous

Numerical and experimental study of isothermal water flow downstream of split-type spacer grids in rod bundles. OECD/NEA benchmark MATiS-H

  • 1. Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany)

Description

Single phase water flow in a 5 x 5 rod bundle is studied within the OECD/NEA benchmark MATiS-H (Measurement and Analysis of Turbulent Mixing in Subchannels - Horizontal). In the benchmark two types of spacer grids are used in the tests, the swirl type and the split type. The flow behind these spacers is investigated for the benchmark study. Comparisons of some CFD results performed in Karlsruhe Institute of Technologie (KIT) with experimental results obtained by KAERI (Korea Atomic Energy Research Institute) are presented for the split type grids. Velocities in three directions along selected lines are measured and compared to CFD results. Numerical results are obtained by using the STAR CCM+ -CFD code. The Realized k-ε model is used for this study. Comparisons with experimental results show quantitative and qualitative agreement for the averaged values of velocity components in the compared regions. (orig.)

Part of:
Annual meeting on nuclear technology 2013. Documentation

Additional details

Additional titles

Original title (English)
Jahrestagung Kerntechnik 2013. Dokumentation

Publishing Information

Imprint Title
Annual meeting on nuclear technology 2013. Documentation
Imprint Pagination
1142 p.
Journal Page Range
4 p.

Conference

Title
Annual meeting on nuclear technology 2013
Original Conference Title
Jahrestagung Kerntechnik 2013
Dates
14-16 May 2013
Place
Berlin (Germany)

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
45049718
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BENCHMARKS; COMPUTERIZED SIMULATION; FLOW MODELS; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL ELEMENT CLUSTERS; FUEL RODS; MIXING; NUMERICAL ANALYSIS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SPACERS; SPECIFICATIONS; TURBULENCE; TURBULENT FLOW
Descriptors DEC
FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENTS; MATHEMATICAL MODELS; MATHEMATICS; MECHANICS; REACTOR COMPONENTS; SAFETY; SIMULATION

Optional Information

Notes
Imprint:Jahrestagung Kerntechnik 2013. Dokumentation