Pretest analysis of natural circulation on the PWR model PACTEL with horizontal steam generators
A new tests facility - parallel channel tests loop (PACTEL)- has been designed and built to simulate the major components and system behavior of pressurized water reactors (PWRs) during postulated small- and medium-break loss-of-coolant accidents. Pretest calculations have been performed for the first test series, and the results of these calculations are being used for planning experiments, for adjusting the data acquisition system, and for choosing the optimal position and type of instrumentation. PACTEL is a volumetrically scaled (1:305) model of the VVER-440 PWR. In all the calculated cases, the natural circulation was found to be effective in removing the heat from the core to the steam generator. The loop mass flow rate peaked at 60% mass inventory. The straightening of the loop seals increased the mass flow rate significantly.
- OSTI ID:
- 5874142
- Report Number(s):
- CONF-901101--
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 62; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
Similar Records
ISP33 standard problem on the PACTEL facility
Natural circulation in a VVER reactor geometry: Experiments with the PACTEL facility and Cathare simulations
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
COMPUTER CODES
CONVECTION
COOLING SYSTEMS
DATA ACQUISITION SYSTEMS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLOW RATE
FLUID FLOW
FLUID MECHANICS
FUEL CHANNELS
HEAT EXCHANGERS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MASS TRANSFER
MECHANICS
NATURAL CONVECTION
PLANNING
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MONITORING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
S CODES
SAFETY
SCALE MODELS
SECONDARY COOLANT CIRCUITS
SIMULATION
STEAM GENERATORS
STRUCTURAL MODELS
TEST FACILITIES
THERMAL REACTORS
TWO-PHASE FLOW
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WWER TYPE REACTORS