Published August 2008 | Version v1
Journal article

Downcomer boiling phenomena during the reflood phase of a large-break LOCA for the APR1400

  • 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.2007.10.024

Additional 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.