TRAC-P1A predictions of the Battelle-Frankfurt top blowdown test. [PWR]
Conference
·
OSTI ID:6070251
A top blowdown vessel experiment carried out in West Germany (Battelle Institute at Frankfurt) has been selected as part of the independent assessment of TRAC-P1A. The experiment provides the data necessary for evaluating the code's capabilities in predicting single- and two-phase choked flow through a nozzle as well as nonequilibrium two-phase flow in a vertical pipe.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6070251
- Report Number(s):
- BNL-NUREG-28127; CONF-801107-17; ON: TI85004725
- Country of Publication:
- United States
- Language:
- English
Similar Records
Independent assessment of TRAC code with various blowdown experiments
TRAC-P1A Developmental Assessment
Ability of the TRAC-P1A computer program to predict blowdown, refill, and reflood phenomena during Semiscale Mod-1 experiments. [PWR]
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:5998546
TRAC-P1A Developmental Assessment
Technical Report
·
Sun Sep 30 20:00:00 EDT 1979
·
OSTI ID:5928702
Ability of the TRAC-P1A computer program to predict blowdown, refill, and reflood phenomena during Semiscale Mod-1 experiments. [PWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5283595
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
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COMPUTER CALCULATIONS
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ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
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NOZZLES
PRESSURE GRADIENTS
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REACTOR COOLING SYSTEMS
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SAFETY
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CALCULATIONS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
NOZZLES
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS