Thermohydraulic investigations by decay heat removal systems
- 1. Kernforschungszentrum Karlsruhe GmbH Institut fur Reaktorbaulemente, Postfach 3640, 7500 Karsruhe 1 (Germany, F.R.)
- 2. Power Reactor and Nuclear Fuel Development Corporation Oarai Engineering Center, Oarai (Japan)
- 3. Kernforschungszentrum Karlsruhe GmbH, Institut fur Reaktorbauelemente, Postfach 3640, 7500 Karlsruhe 1 (Germany, F.R.)
Description
This paper reports, to examine the function of the safety-related SNR-2 decay heat removal concept, natural convection experiments performed in two-and three-dimensional water models, scaled 1:20, under conditions of symmetric and nonsymmetric loads of the immersed coolers installed in the upper plenum at 180-deg positions with respect to each other. The temperature and velocity distributions were measured and the flow patterns recorded for different configurations of the instrumented plug. For symmetric load conditions, symmetric temperature and flow distributions were measured in two- and three-dimensional models. Nonsymmetric load conditions produce remarkable temperature differences between the two separated plenums of the two-dimensional model if fluid circulation is suppressed by a closed plug. An open plug allows fluid to pass through and shows lower temperature differences. In contrast, in the three-dimensional experiment, azimuthal fluid flow inside the plenum prevails even with the plug closed, and identical temperature distributions are measured. The calculations using the COMMIX-1B code are generally in good agreement with the measurements
Additional details
Additional titles
- Subtitle (English)
- By natural convection for liquid-metal fast breeder reactors
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 88
- Journal Issue
- 1
- Series
- Nucl. Technol.
- Journal Page Range
- 75-86
- ISSN
- 0029-5450
- CODEN
- NUTYB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21059274
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- AFTER-HEAT REMOVAL; C CODES; DYNAMIC LOADS; HEAT EXCHANGERS; LMFBR TYPE REACTORS; NATURAL CONVECTION; REACTOR COOLING SYSTEMS; REACTOR SAFETY EXPERIMENTS; TEMPERATURE DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; VELOCITY
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS