Simulators, Volume 10Society for Computer Simulation, 1993 - Computer simulation |
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Page 386
SEISMIC ANALYSIS AND VISUALIZATION FOR PIPINGS IN NUCLEAR POWER PLANTS Tomonori Kono and Masuhiko Kobatake NUPEC / INS 3-17-1 , Toranomon , Minato - ku , Tokyo , 105 , Japan Optical disk image recording unit Hardware System used for ...
SEISMIC ANALYSIS AND VISUALIZATION FOR PIPINGS IN NUCLEAR POWER PLANTS Tomonori Kono and Masuhiko Kobatake NUPEC / INS 3-17-1 , Toranomon , Minato - ku , Tokyo , 105 , Japan Optical disk image recording unit Hardware System used for ...
Page 387
Analysis Code The INS ' developed SANPIP code has been used for analysis . The code represents three - dimensional piping systems in a model of beam ... Analysis for Pipings Analysis and Result The schematic flow of the seismic analysis 387.
Analysis Code The INS ' developed SANPIP code has been used for analysis . The code represents three - dimensional piping systems in a model of beam ... Analysis for Pipings Analysis and Result The schematic flow of the seismic analysis 387.
Page 388
Analysis and Result The schematic flow of the seismic analysis for pipings is first shown in Figure 2. First , the piping is modeled by beams and lumped masses . Then , the stress due to dead- load , internal pressure and thermal load ...
Analysis and Result The schematic flow of the seismic analysis for pipings is first shown in Figure 2. First , the piping is modeled by beams and lumped masses . Then , the stress due to dead- load , internal pressure and thermal load ...
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 |
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accident algorithm analysis assessment auxiliary feedwater Average axial behavior calculated components configuration control room control system coolant developed drift flux dtime dynamic effects engineering enthalpy EOPS equations error evaluation experiment feedwater Figure flow rate fluid fuel function genetic algorithm Hamaoka hardware heat transfer hydraulic network initial input instructor integration interface Kalman Filter loop main steam mass flow method Mihama-2 module momentum neutron nodal power nodes nuclear power plant operation training output panels parameters performance phase plant data power plant simulators prediction pressure pressurized water reactor primary procedures process computer reactor coolant reactor power RELAP5/MOD3 response safety scenarios scram secondary simulation models specific start-up steam collector step tank temperature THEATRe thermal hydraulic training simulator transient tube turbine trip upgrade utilities validation values valves variables VVER xenon