Published May 2018 | Version v1
Miscellaneous

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.

Part of:
Proceedings of the KNS 2018 Spring Meeting

Additional details

Identifiers

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