Published 2002 | Version v1
Book

Direct ECC Bypass Phenomena During LBLOCA Reflood Phase Observed in the MIDAS Test: Facility

  • 1. Korea Atomic Energy Research Institute, 150, Dukjin-Dong, Yusong-Gu, Taejon 305-353 (Korea, Republic of)

Description

One of the advanced design features of the APR-1400, direct vessel injection (DVI) system is being considered instead of conventional cold leg injection (CLI) system. It is known that the DVI system greatly enhances the reliability of the emergency core cooling (ECC) system. However, there is still a dispute on its performance in terms of water delivery to the reactor core during the reflood phase of a large-break loss-of-coolant accident (LOCA). Thus, experimental validation is in progress. In this paper, test results of a direct ECC bypass performed in the steam-water test facility called MIDAS (Multi-dimensional Investigation in Downcomer Annulus Simulation) is presented. The test condition is determined, based on the preliminary analysis of TRAC code, by applying the 'modified linear scaling method' with the 1/4.93 length scale. From the tests, ECC direct bypass fraction, steam condensation rate and information on the flow distribution in the upper annulus downcomer region is obtained. (authors)

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers - ASME
Imprint Place
New York (United States)
Imprint Pagination
7 p.

Conference

Title
10. international conference on nuclear engineering
Acronym
ICONE-10
Dates
14-18 Apr 2002
Place
Arlington - Virginia (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
39086216
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BYPASSES; CONTAINERS; DELIVERY; DESIGN; DISTRIBUTION; ECCS; INJECTION; LEGS; LENGTH; LOSS OF COOLANT; PERFORMANCE; REACTOR CORES; RELIABILITY; SCALING; STEAM; TEST FACILITIES; VALIDATION; WATER
Descriptors DEC
ACCIDENTS; BODY; DIMENSIONS; ENGINEERED SAFETY SYSTEMS; HYDROGEN COMPOUNDS; INTAKE; LIMBS; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; TESTING