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