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Bian, S.H.; Thurgood, M.J.
Pacific Northwest Labs., Richland, WA (USA); Numerical Applications, Inc., Richland, WA (USA)1984
Pacific Northwest Labs., Richland, WA (USA); Numerical Applications, Inc., Richland, WA (USA)1984
AbstractAbstract
[en] The purpose of the COBRA/TRAC simulation of Semiscale Test S-UT-5 is to study the capability of COBRA/TRAC to predict the system response in a 2.5% small-break LOCA (SBLOCA) and the effects of upper head injection (UHI) on core behavior. In addition, it serves to verify the capability of the code to simulate the integrated configuration of a PWR. The COBRA/TRAC code uses a set of compressible three-dimensional, two-fluid, three-field equations to represent two-phase flow in the reactor vessel and steam generators. The three fields are the vapor field, the continuous liquid field, and the liquid drop field. A five-equation drift flux model is used to model fluid flow in the primary system piping, pressurizer, pumps, and accumulators. The heat generation rate of the core is specified by input and no reactor kinetics calculations are included in the solution
Primary Subject
Source
Nov 1984; 6 p; Annual meeting of the American Nuclear Society; Boston, MA (USA); 9-14 Jun 1985; CONF-850610--49; Available from NTIS, PC A02/MF A01 - GPO as TI85017897
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
COMPUTER CODES, COMPUTERIZED SIMULATION, CONTAINERS, HEAT TRANSFER, HYDRAULICS, LOSS OF COOLANT, PIPES, PRESSURIZERS, PRIMARY COOLANT CIRCUITS, PUMPS, PWR TYPE REACTORS, REACTOR CORES, REACTOR SAFETY, REACTOR VESSELS, RISK ASSESSMENT, STEAM GENERATORS, THREE-DIMENSIONAL CALCULATIONS, TWO-PHASE FLOW, VALVES
ACCIDENTS, BOILERS, CONTROL EQUIPMENT, COOLING SYSTEMS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, EQUIPMENT, FLOW REGULATORS, FLUID FLOW, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SAFETY, SIMULATION, THERMAL REACTORS, VAPOR GENERATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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