Richardson number criteria for direct-contact-condensation-induced thermal stratification using visualization

被引:16
作者
Jo, Byeongnam [1 ]
Erkan, Nejdet [2 ]
Okamoto, Koji [2 ]
机构
[1] Ajou Univ, Dept Mech Engn, Suwon, South Korea
[2] Univ Tokyo, Dept Nucl Engn & Management, 7-3-1 Hongo, Tokyo, Japan
关键词
Thermal stratification; Richardson number; Direct contact condensation; Visualization; Suppression pool; SUPPRESSION POOL; STEAM CONDENSATION; FLOW PATTERNS; PRESSURE; SYSTEM; WATER;
D O I
10.1016/j.pnucene.2019.103095
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This study aims to suggest a dimensionless number to determine the formation and disappearance of thermal stratification induced by direct contact condensation in a 1/20 scaled-down suppression pool of the Fukushima Daiichi nuclear power plant. The modified Richardson number, which represents the ratio of buoyancy force to inertia of steam, was employed to explain the thermal stratification in the suppression pool. Steam condensation experiments were performed at both sub-atmospheric and atmospheric pressures. A blow-down pipe with an inner diameter of 12.7 mm was used to inject and condense steam in the suppression pool. The effects of steam mass on the thermal stratification behaviors were examined by varying the steam mass flow rate (mass flux) from 0.50 kg/hr (1.10 kg/m(2).s) to 2.50 kg/hr (5.48 kg/m(2).s). The steam condensation was visualized using a high-speed camera. In the results, thermal stratification was successfully reproduced in this study, and it was observed that the behaviors of thermal stratification (vertical temperature profile) was affected by the steam mass flow rate and the subcooling temperature. The Richardson number was evaluated by measuring the size and frequency of steam bubbles. The time evolution of the Richardson number was analyzed with vertical temperature profiles of water in the suppression pool. The critical Richardson number, which determines the formation and disappearance of thermal stratification, was suggested to be of the order of 1.
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页数:10
相关论文
共 24 条
[1]  
[Anonymous], 2012, Fukushima Nuclear Accident Analysis Report
[2]   BOUNDARIES BETWEEN REGIMES OF PRESSURE OSCILLATION INDUCED BY STEAM CONDENSATION IN PRESSURE SUPPRESSION CONTAINMENT [J].
AYA, I ;
NARIAI, H .
NUCLEAR ENGINEERING AND DESIGN, 1987, 99 :31-40
[3]   PRESSURE AND FLUID OSCILLATIONS IN VENT SYSTEM DUE TO STEAM CONDENSATION .2. HIGH-FREQUENCY COMPONENT OF PRESSURE OSCILLATIONS IN VENT TUBES UNDER AT CHUGGING AND CONDENSATION OSCILLATION [J].
AYA, I ;
KOBAYASHI, M ;
NARIAI, H .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1983, 20 (03) :213-227
[4]   Effect of non-condensable gas on thermal stratification and flow patterns in suppression pool [J].
Cai, Jiejin ;
Jo, Byeongnam ;
Erkan, Nejdet ;
Okamoto, Koji .
NUCLEAR ENGINEERING AND DESIGN, 2016, 300 :117-126
[5]   A REGIME MAP FOR DIRECT CONTACT CONDENSATION [J].
CHAN, CK ;
LEE, CKB .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 1982, 8 (01) :11-20
[6]   Three-dimensional condensation regime diagram for direct contact condensation of steam injected into water [J].
de With, A. Petrovic ;
Calay, R. K. ;
de With, G. .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2007, 50 (9-10) :1762-1770
[7]   Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: Thermal-hydraulic analysis [J].
Fernandez-Moguel, L. ;
Rydl, A. ;
Lind, T. .
ANNALS OF NUCLEAR ENERGY, 2019, 123 :59-77
[8]   Pressure suppression pool mixing in passive advanced BWR plants [J].
Gamble, RE ;
Nguyen, TT ;
Shiralkar, BS ;
Peterson, PF ;
Greif, R ;
Tabata, H .
NUCLEAR ENGINEERING AND DESIGN, 2001, 204 (1-3) :321-336
[9]   Experimental study on steam chugging phenomenon in a vertical sparger [J].
Gregu, Giuseppe ;
Takahashi, Minoru ;
Pellegrini, Marco ;
Mereu, Riccardo .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 2017, 88 :87-98
[10]  
Hoshi H., 2012, FUK MIN C NUCL SAF D