Investigation of fluid mixing with direct vessel injection
Creators
- 1. Korea Atomic Energy Research Institute, PO Box 105, Yuseong, Taejon (Korea, Republic of)
Description
The object of this work is to investigate fluid mixing phenomena as they related to pressurized thermal shock (PTS) in a pressurized water reactor vessel downcomer during transient cooldown with direct vessel injection (DVI), using test models. The test model designs were based on ABB Combustion Engineering (CE) System 80+ reactor geometry. A cold-leg, small-break loss-of-coolant accident (LOCA) and a main steam line break were selected as the potential PTS events for the ABB-CE System 80+. This work consists of two parts. The first part provides the visualization tests of the fluid mixing between DVI fluids and existing coolant in the downcomer region, and the second part presents the results of thermal mixing tests with DVI in the other test model. Flow visualization tests with DVI have clarified the physical interaction between DVI fluid and primary coolant during transient cooldown. A significant temperature drop was observed in the downcomer during the tests of a small-break LOCA. The measured transient temperature profiles compare well with the predictions from the ppercase[remix] code for a small-break LOCA, and with the calculations from the ppercase[commix]- ppercase[1b] code for a stream line break event. ((orig.))
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 149
- Journal Issue
- 1-3
- Journal Page Range
- p. 299-311.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics (Nureth-6).
- Dates
- 5-8 Oct 1993.
- Place
- Grenoble (France).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 26016945
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORRELATIONS; FLOW MODELS; FLOW RATE; FLOW VISUALIZATION; JETS; LOSS OF COOLANT; PWR TYPE REACTORS; TEMPERATURE MEASUREMENT; THERMAL SHOCK; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FLUID FLOW; MATHEMATICAL MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS