Simulators VIII: Proceedings of the Simulation Multiconference on Simulators International VIII, 1-5 April 1991, New Orleans, LouisianaAriel Sharon |
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Page 172
... density of the mixture , average density of the fluid , average density of the inert gas , internal energy of the mixture , the enthalpy of the gas phase . The key moment for determining parameters on the boundary of the cells is the ...
... density of the mixture , average density of the fluid , average density of the inert gas , internal energy of the mixture , the enthalpy of the gas phase . The key moment for determining parameters on the boundary of the cells is the ...
Page 173
... density of the mixture , average density of the fluid , average density of the inert gas , internal energy of the mixture , the enthalpy of the gas phase . The key moment for determining parameters on the boundary of the cells is the ...
... density of the mixture , average density of the fluid , average density of the inert gas , internal energy of the mixture , the enthalpy of the gas phase . The key moment for determining parameters on the boundary of the cells is the ...
Page 256
... density Combining the three previous equations gives an equation to calculate the steam pressure which will apply for both wet and superheated steam . v , = vg ( P. ) x + vƒ ( P , ) ( 1 − x ) eq.6 P , = 1.2529 ( Max ( h ,, h , ( xd ...
... density Combining the three previous equations gives an equation to calculate the steam pressure which will apply for both wet and superheated steam . v , = vg ( P. ) x + vƒ ( P , ) ( 1 − x ) eq.6 P , = 1.2529 ( Max ( h ,, h , ( xd ...
Contents
Performance Modelling for a Simulator Upgrade 3 Ankur R Hajare | 14 |
Software Maintenance Techniques For Nuclear Power 20 Scott G Whitson | 20 |
Elimination of the Vector Processor From the Monticello 36 Manshik Song | 36 |
Copyright | |
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algorithm analysis application Argonne National Laboratory artificial intelligence calculated capability CETRAN CIN sub-model complex component condensation configuration control room coolant core database decay heat density displays dynamic effects energy engineering enthalpy environment equations error feedwater Figure fission product flow fluid FORTRAN fuel function graphics hardware heat transfer HMMWV implementation initial input Instructor Station integration interaction interface liquid loop malfunctions mass mass flow rate matrix method module momentum monitoring neutron nodal nodes nuclear power plant OPERAS parameters performance phase physical pressure primary problem procedures processor pseudocode pump RELAP5 response RTMC safety scenario severe accident Silicon Graphics simulation models simulation software solution specific steam step subsystem supercomputer techniques temperature thermal-hydraulic tion training simulator transient utility validation values valve variables workstations