Benchmarking of flowtran with Mark-22 mockup flow excursion test data from Babcock Wilcox
Version 16.2 of the FLOWTRAN code with a Savannah River Site (SRS) working criterion (St=0.00455) for the onset of significant void (OSV) was benchmarked against power and flow excursion data derived from tests at the Babcock Wilcox Alliance Research Center test facility. This document presents analyses which show that FLOWTRAN accurately predicts the mockup test assembly thermal-hydraulic behavior during the steady state and LOCA transient conditions, and that FLOWTRAN with a Savannah River Site (SRS) working limits criterion (St=0.00455) conservatively predicts the OFI power.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5035326
- Report Number(s):
- WSRC-TR-90-97; ON: DE92017945
- Country of Publication:
- United States
- Language:
- English
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Benchmarking of FLOWTRAN with Mark-22 mockup flow excursion test data from Babcock Wilcox
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Technical Report
·
Fri Nov 01 00:00:00 EST 1991
·
OSTI ID:5035326
Benchmarking of FLOWTRAN with Mark-22 mockup flow excursion test data from Babcock & Wilcox
Technical Report
·
Fri Nov 01 00:00:00 EST 1991
·
OSTI ID:5035326
Benchmarking of flowtran with Mark-22 mockup flow excursion test data from Babcock & Wilcox
Technical Report
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Fri Jun 01 00:00:00 EDT 1990
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OSTI ID:5035326
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FLUID FLOW
STABILITY
PRODUCTION REACTORS
LOSS OF COOLANT
COMPUTER CALCULATIONS
EXCURSIONS
F CODES
HEAT TRANSFER
HYDRAULICS
SAVANNAH RIVER PLANT
SCRAM
VOIDS
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR SHUTDOWN
REACTORS
SHUTDOWN
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FLUID FLOW
STABILITY
PRODUCTION REACTORS
LOSS OF COOLANT
COMPUTER CALCULATIONS
EXCURSIONS
F CODES
HEAT TRANSFER
HYDRAULICS
SAVANNAH RIVER PLANT
SCRAM
VOIDS
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR SHUTDOWN
REACTORS
SHUTDOWN
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors