Simulators, Volume 10Society for Computer Simulation, 1993 - Computer simulation |
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Page 151
... equations are solved for each node while the mixture conservation of momentum equation is solved for each link . Phasic flow rates are de- termined from the drift flux correlation and the mixture momentum equation . Convected quanti ...
... equations are solved for each node while the mixture conservation of momentum equation is solved for each link . Phasic flow rates are de- termined from the drift flux correlation and the mixture momentum equation . Convected quanti ...
Page 161
... equations , i.e. , two mass , two energy , and one mixture momentum equations . The required state equations are also the complete RELAP5 / MOD3 equations and the water property range covers all possible water conditions , including ...
... equations , i.e. , two mass , two energy , and one mixture momentum equations . The required state equations are also the complete RELAP5 / MOD3 equations and the water property range covers all possible water conditions , including ...
Page 189
... equations can be re - arranged : Continuity equation for water , steam , and gas : i = 1 , 2 , 3 = α , Energy ... equations by three . Additional equations needed to have a closed set . These equations are be obtained from the ...
... equations can be re - arranged : Continuity equation for water , steam , and gas : i = 1 , 2 , 3 = α , Energy ... equations by three . Additional equations needed to have a closed set . These equations are be obtained from the ...
Contents
Role of Simulators in Safe Operation of Nuclear Power Plants | 3 |
SIMULATION AND SIMULATORS AT NUCLEAR POWER PLANTS IN EASTERN EUROPE | 9 |
Safety Analyses for VVER Type Reactors with the Reactor | 18 |
Copyright | |
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algorithm analysis application assessment axial behavior calculated compact simulator components configuration control room control system coolant core crew database developed display distribution dynamic effects EMCAP engineering enthalpy EOPS equations error evaluation feedwater Figure flow rate flux FORTRAN fuel function graphics hardware heat transfer human reliability hydraulic network implemented improve initial input instructor integration interactive interface Kalman Filter loop main steam malfunctions mass flow method Mihama-2 module monitoring neutron nodal nodes nuclear power plant operator training output panel parameters performance phase plant data power plant simulators prediction pressure pressurized water reactor primary procedures process computer pump reactor coolant real-time response safety scenarios scram simulation models specific step tank temperature THEATRe thermal hydraulic training simulator transient trip turbine UNIX upgrade utilities validation values valves variables vessel VVER