TY - GEN
T1 - Validation of the APROS thermal-hydraulics against the PACTEL test facility
AU - Plitt, Herkko
AU - Porkholm, Kari
AU - Hänninen, Markku
PY - 1997
Y1 - 1997
N2 - APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Research Centre of Finland (VTT) and IVO Power Engineering Ltd (IVO PE) for process and automation design, safety analysis and training simulator applications. Up to now the APROS development has required more than 150 man years. APROS applications include nuclear and fossil power plant models, but also chemical as well as pulp and paper processes can be modeled. PACTEL - PArallel Channel TEst Loop - is an experimental integral test facility for VVER-440 nuclear power plants. VVER nuclear power plants have some special features like hexagonal fuel assemblies and horizontal steam generators. Therefore PACTEL experiments provide for VVER-purposes unique information which can not be obtained with normal PWR integral test facilities. PACTEL experiments are also very important for computer codes, like APROS, for VVER validation.
AB - APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Research Centre of Finland (VTT) and IVO Power Engineering Ltd (IVO PE) for process and automation design, safety analysis and training simulator applications. Up to now the APROS development has required more than 150 man years. APROS applications include nuclear and fossil power plant models, but also chemical as well as pulp and paper processes can be modeled. PACTEL - PArallel Channel TEst Loop - is an experimental integral test facility for VVER-440 nuclear power plants. VVER nuclear power plants have some special features like hexagonal fuel assemblies and horizontal steam generators. Therefore PACTEL experiments provide for VVER-purposes unique information which can not be obtained with normal PWR integral test facilities. PACTEL experiments are also very important for computer codes, like APROS, for VVER validation.
M3 - Conference article in proceedings
T3 - NUREG/CP
SP - 1187
EP - 1194
BT - 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8)
PB - Atomic Energy Society of Japan
CY - Tokyo
T2 - 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics
Y2 - 30 September 1997 through 4 October 1997
ER -