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AbstractAbstract
[en] This report compares the results of the RELAP5/MOD2 analysis with experimental measurements. A simulation of test LP-SB-03 was previously carried out at GDCD using the RELAP5/MOD1 code. RELAP5/MOD2 was developed from RELAP5/MOD1 and contains more sophisticated hydraulic models and constitutive relationships. Comparison of the RELAP5/MOD2 and MOD1 calculations show that RELAP5/MOD2 performs better than RELAP5/MOD1 in a number of key areas; notably mass errors are much reduced, there is improved numerical stability, and improved separator modeling and modeling of accumulator injection. 5 refs., 26 figs
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Jan 1990; 46 p; NTIS, PC A03/MF A01 - GPO as TI90006025; OSTI; INIS
Record Type
Report
Literature Type
Numerical Data
Report Number
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COMPARATIVE EVALUATIONS, COMPUTERIZED SIMULATION, EXPERIMENTAL DATA, FAILURE MODE ANALYSIS, FLOW RATE, FRACTURE MECHANICS, FUEL ELEMENTS, HEAT TRANSFER, HYDRAULICS, INTERNATIONAL COOPERATION, LOSS OF COOLANT, PIPES, PRESSURE DEPENDENCE, PWR TYPE REACTORS, R CODES, REACTOR CORES, REACTOR SAFETY, RESEARCH PROGRAMS, RISK ASSESSMENT, TEMPERATURE DEPENDENCE, TRANSIENTS
ACCIDENTS, COMPUTER CODES, COOPERATION, DATA, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, EVALUATION, INFORMATION, MECHANICS, NUMERICAL DATA, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, SAFETY, SIMULATION, SYSTEM FAILURE ANALYSIS, SYSTEMS ANALYSIS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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