Simulation of a 30-tube once-through steam generator with RELAP5/MOD3 and RELAP5/MOD2 computer codes
- Texas A and M Univ., College Station (United States)
The development and modification of any computer code necessitate assessment and validation of the code. A similar task prevails with the release of the thermal-hydraulic analysis code RELAP5/MOD3. RELAP5/MOD3 has been developed by EG and G Idaho, from its predecessor code RELAP5/MOD2, after identifying certain deficiencies in the latter. The work presented here assesses the RELAP5/MOD3 computer code. The objective of this study is to evaluate the predictions of the RELAP5/MOD2 and RELAP5/MOD3 computer codes, using a model of a full-length, 30-tube once-through steam generator (OTSG). The RELAP5/MOD3 results for the test facility generally show a reasonable agreement with the data for the primary-side temperature profiles. However, the secondary temperature profile predicted by RELAP5/MOD3, at 65% load, compares fairly well with data and is better than the RELAP5/MOD2 results.
- OSTI ID:
- 6780203
- Report Number(s):
- CONF-901101--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 62; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
Similar Records
Steady-state simulations of a 30-tube once-through steam generator with the RELAP5/MOD3 and RELAP5/MOD2 computer codes
RELAP5/MOD2 code modifications to obtain better predictions for the once-through steam generator
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BOUNDARY CONDITIONS
CHEMISTRY
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
CONTROL
COOLING SYSTEMS
CRAY COMPUTERS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MEASURING INSTRUMENTS
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MODIFICATIONS
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PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SECONDARY COOLANT CIRCUITS
SIMULATION
STEADY-STATE CONDITIONS
STEAM GENERATORS
TEMPERATURE CONTROL
TEST FACILITIES
TESTING
THERMAL REACTORS
THERMOCOUPLES
TIME DEPENDENCE
TRANSIENTS
VALIDATION
VAPOR GENERATORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS