ACT-1: a digital program for the analysis of the containment transient during a loss of coolant accident in LWB (LWBR Development Program)
Technical Report
·
OSTI ID:6741551
A description of the Act-I computer program for the prediction of the containment transient resulting from the injection of high enthalpy liquid and heat during a loss-of-coolant accident is given. A finite difference integration is performed over the time of the transient accounting for heat and mass additions from input tables, for heat transfer to various heat sinks including simulated safeguards, and for leakage from the container to the atmosphere. The output of the FLASH program has been modified to present the data in a readily usable form as input tables of heat and mass addition to Act-I. Some numerical comparisons with existing data are made. (NSA 21: 30177)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 6741551
- Report Number(s):
- WAPD-TM-693
- Country of Publication:
- United States
- Language:
- English
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ACT-I: A DIGITAL PROGRAM FOR THE ANALYSIS OF THE CONTAINMENT TRANSIENT DURING A LOSS OF COOLANT ACCIDENT IN LWB.
HOTROD: a computer program for subchannel analysis of coolant flow in rod bundles (LWBR Development Program)
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Mon Jul 01 00:00:00 EDT 1968
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OSTI ID:6760956
ACT-I: A DIGITAL PROGRAM FOR THE ANALYSIS OF THE CONTAINMENT TRANSIENT DURING A LOSS OF COOLANT ACCIDENT IN LWB.
Technical Report
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Sat Dec 31 23:00:00 EST 1966
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OSTI ID:4355348
HOTROD: a computer program for subchannel analysis of coolant flow in rod bundles (LWBR Development Program)
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Wed Oct 31 23:00:00 EST 1973
·
OSTI ID:7010383
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
A CODES
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
CONTAINMENT
LOSS OF COOLANT
LWBR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
A CODES
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
CONTAINMENT
LOSS OF COOLANT
LWBR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS