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SIMULATION AND SIMULATORS AT NUCLEAR POWER PLANTS IN EASTERN EUROPE
WERReactors Ulrich Rohde
Mathematical Modeling of the Transient and Accident 36 P Kril
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algorithm analysis application assessment auxiliary feedwater axial behavior calculated compact simulator components configuration control room control system core crew database developed display distribution dynamic effects EMCAP engineering enthalpy EOPs equations error evaluation feedwater 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 method Mihama-2 module neutron nodal nodes nuclear power plant operator training output panels parameters performance phase power plant simulators predicted pressure pressurized water reactor primary procedures process computer pump reactor coolant real-time response safety scenarios scram severe accident simulation models specific step temperature THEATRe thermal hydraulic training simulator transient trip turbine UNIX upgrade utilities validation values valves variables vessel VVER