File Download

There are no files associated with this item.

  • Find it @ UNIST can give you direct access to the published full text of this article. (UNISTARs only)

Views & Downloads

Detailed Information

Cited time in webofscience Cited time in scopus
Metadata Downloads

Full metadata record

DC Field Value Language
dc.citation.conferencePlace CS -
dc.citation.conferencePlace Prague; Czech Republic -
dc.citation.title 2014 22nd International Conference on Nuclear Engineering, ICONE 2014 -
dc.citation.volume 2B -
dc.contributor.author Kim, Hyoung Tae -
dc.contributor.author Seo, Han -
dc.contributor.author Im, Sunghyuk -
dc.contributor.author Rhee, Bo Wook -
dc.contributor.author Cha, Jae Eun -
dc.date.accessioned 2023-12-20T00:10:57Z -
dc.date.available 2023-12-20T00:10:57Z -
dc.date.created 2014-12-03 -
dc.date.issued 2014 -
dc.description.abstract As a CANDU6 reactor has a high pressure primary cooling system and an independently cooled moderator system, the moderator in the calandria would act as a supplementary heat sink during a loss of coolant accident (LOCA) if the primary cooling and emergency coolant injection systems fail to remove the decay heat from the fuel. For the safety concern it is required to predict the 3-dimensional velocity and temperature distribution of moderator fluid to confirm the effectiveness of moderator heat sink. Korea Atomic Energy Research Institute (KAERI) is carrying out a scaled-down moderator test program to simulate the CANDU6 moderator circulation phenomena during steady state operation and accident conditions. This research program includes the construction of the Moderator Circulation Test (MCT) facility, production of the validation data for self-reliant CFD tools, and development of optical measurement system using the Particle Image Velocimetry (PIV). In the present work the PIV technique is used to measure the velocity distributions in the scaled moderator tank of MCT under iso-thermal test conditions. The preliminary PIV measurement data are obtained and compared with CFX code predictions. -
dc.identifier.bibliographicCitation 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, v.2B -
dc.identifier.doi 10.1115/ICONE22-31140 -
dc.identifier.isbn 978-079184591-2 -
dc.identifier.scopusid 2-s2.0-84911424736 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/51333 -
dc.language 영어 -
dc.publisher American Society of Mechanical Engineers (ASME) -
dc.title Experimental study of moderator circulation in candu6 Calandria tank -
dc.type Conference Paper -
dc.date.conferenceDate 2014-07-07 -

qrcode

Items in Repository are protected by copyright, with all rights reserved, unless otherwise indicated.