Downcomer boiling phenomena during the reflood phase of a large-break LOCA for the APR1400
Creators
- 1. Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Dukjin-dong 150, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)
Description
Downcomer boiling phenomena in a conventional pressurized water reactor has an important effect on the transient behavior of a postulated large-break LOCA (LBLOCA), because it can degrade the hydraulic head of the coolant in the downcomer and consequently affect the reflood flow rate for a core cooling. To investigate the thermal hydraulic behavior in the downcomer region, a test program for a downcomer boiling (DOBO) is being progressed for the reflood phase of a postulated LBLOCA. Test facility was designed as a one side heated rectangular channel which adopts a full-pressure, full-height, and full-size downcomer-gap approach, but with the circumferential length reduced 47.08-fold. The test was performed by dividing it into two-phases: (I) visual observation and acquisition of the global two-phase flow parameters and (II(a)) measurement of the local bubble flow parameters on the measuring planes along five elevations. In the present paper, the test results of Phase-I and a part of Phase-II(a) were introduced
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2007.10.024Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2007.10.024;
- PII
- S0029-5493(08)00042-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 8
- Journal Page Range
- p. 2064-2074
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 14. international conference on nuclear energy
- Acronym
- ICONE-14
- Dates
- 17-20 Jul 2006
- Place
- Miami, FL (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40005607
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING; BUBBLES; COOLANTS; COOLING; FLOW RATE; HEIGHT; LENGTH; LOSS OF COOLANT; PWR TYPE REACTORS; TEST FACILITIES; THERMAL HYDRAULICS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; DIMENSIONS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.