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)
Related Researcher

FynanDouglas

Fynan, Douglas A.
Nuclear Science, Simulation & Safety Lab.
Read More

Views & Downloads

Detailed Information

Cited time in webofscience Cited time in scopus
Metadata Downloads

Full metadata record

DC Field Value Language
dc.citation.endPage 452 -
dc.citation.startPage 438 -
dc.citation.title NUCLEAR ENGINEERING AND DESIGN -
dc.citation.volume 310 -
dc.contributor.author Fynan, Douglas A. -
dc.contributor.author Ahn, Kwang-Il -
dc.date.accessioned 2023-12-21T22:48:12Z -
dc.date.available 2023-12-21T22:48:12Z -
dc.date.created 2018-08-29 -
dc.date.issued 2016-12 -
dc.description.abstract Characteristic pressure drop-flow rate curves are generated for all row numbers of the OPR1000 steam generators (SGs), representative of Combustion Engineering (CE) type SGs featuring square bend U-tubes. The pressure drop-flow rate curves are applicable to severe accident natural circulations of single-phase superheated steam during high pressure station blackout sequences with failed auxiliary feedwater and dry secondary side which are closely related to the thermally induced steam generator tube rupture event. The pressure drop-flow rate curves which determine the recirculation rate through the SG tubes are dependent on the tube bundle geometry and hydraulic diameter of the tubes. The larger CE type SGs have greater variation of tube length and height as a function of row number with forward flow of steam favored in the longer and taller high row number tubes and reverse flow favored in the short low row number tubes. Friction loss, natural convection heat transfer coefficients, and temperature differentials from the primary to secondary side are dominant parameters affecting the recirculation rate. The need for correlation development for natural convection heat transfer coefficients for external flow over tube bundles currently not modeled in system codes is discussed. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND DESIGN, v.310, pp.438 - 452 -
dc.identifier.doi 10.1016/j.nucengdes.2016.11.004 -
dc.identifier.issn 0029-5493 -
dc.identifier.scopusid 2-s2.0-85002713927 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/24697 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S0029549316304356?via%3Dihub -
dc.identifier.wosid 000390736400035 -
dc.language 영어 -
dc.publisher ELSEVIER SCIENCE SA -
dc.title Pressure drop-flow rate curves for single-phase steam in Combustion Engineering type steam generator U-tubes during severe accidents -
dc.type Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -

qrcode

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