Published 2009 | Version v1
Miscellaneous

Droplet measurement and generation techniques in a rod bundle geometry for a reflood heat transfer test

  • 1. KAERI, Daejeon (Korea, Republic of)

Description

During the reflood phase of a postulated loss of coolant accident in a nuclear reactor, the entrainment of liquid droplets can occur at a quench front of a reflooding water. It is widely recognized that the behavior of the entrained droplet crucially affects the reflood heat transfer by decreasing the superheated steam temperature and interacting with a rod bundle and spacer grids. This paper describes a measurement and a generation techniques that were proposed to investigate droplet behavior in a rod bundle geometry. An image processing technique and a vibrating nozzle method were selected for the droplet measurement and generation, respectively, considering the applicability to the test sections. A preliminary test for the measurement method was performed in a 2 x 2 rod array. The proposed droplet generation method was also tested independently in a rectangular channel. These test results were presented in this paper

Part of:
Proceedings for the Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4)

Additional details

Publishing Information

Publisher
KAERI
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings for the Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4)
Imprint Pagination
534 p.
Journal Page Range
p. 236-243

Conference

Title
4. Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics
Dates
18-20 May 2009
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40082000
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DROPLETS; FUEL ELEMENT CLUSTERS; GEOMETRY; HEAT TRANSFER; LOSS OF COOLANT; REACTORS
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; FUEL ASSEMBLIES; MATHEMATICS; PARTICLES; REACTOR ACCIDENTS

Optional Information

Notes
6 refs, 17 figs