Validation of Turbulent Momentum Mixing of MATRA-S Code for CNEN 4x4 Single Phases Flow Mixing
- 1. King Abdullah City for Atomic and Renewable Energy, Riyadh (Saudi Arabia)
- 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The calculation of various turbulent flow mixing coefficients has been done to evaluate the exit velocity distributions for corner, side and central subchannels with the measurement results for each subchannel. Furthermore, the effect of the turbulent flow mixing coefficient will be as the main point of this study. CNEN4x4 is an experiment which was done in unheated assembly under single-phase flow condition which had been performed by Studsvik Laboratory to obtain information about the heat transfer due to the flow turbulent mixing between adjacent subchannels under a single-phase flow regime. MATRA-S predicted accurately the flow velocities profiles along the axial direction, by comparing the measured data using the optimum TDC value with the maximum percentage error which turned to be 3.0 %. The comparison with CNEN4x4 measurement was successfully validated by using the appropriate model applied in MATRA-S code which is EM turbulent model and optimizing its coefficient.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Spring Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Spring Meeting of the KNS
- Dates
- 16-18 May 2018
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50059181
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCURACY; COMPUTER CALCULATIONS; DESIGN; M CODES; MIXING; PWR TYPE REACTORS; REACTOR CORES; THERMAL HYDRAULICS; TURBULENT FLOW; VALIDATION; VELOCITY
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs, 4 figs, 2 tabs