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 un...
The upper tie plate countercurrent flow limitation correlation of APROS was validated against experi...
This paper presents the comparison between the measured and calculated (APROS code version 5.04) res...
The characteristics of the thermohydraulic solutions in APROS are considered for the nuclear power p...
APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Resea...
PACTEL facility has been used quite extensively for validation of the thermal hydraulic part of APRO...
The PACTEL is a test facility designed to model the thermal-hydraulic behaviours of the Soviet-desig...
APROS is a multifunctional simulator, suitable for various tasks throughout the complete power plant...
APROS (Advanced PROcess Simulator) is the computer simulation system for process and automation syst...
The European Commission fourth framework programme project ‘Assessment of passive safety injection s...
APROS code is a multifunctional process simulator which combines System Thermal-Hydraulic (STH) capa...
The paper describes the capabilities of APROS code in the simulation of the VVER-91 concept. The VVE...
The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to s...
APROS is the product being developed in the Process Simulators project of Imatran Voima Co. and Tech...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
VTT Energy, in co-operation with Lappeenranta University of Technology, has run experiments in the P...
The upper tie plate countercurrent flow limitation correlation of APROS was validated against experi...
This paper presents the comparison between the measured and calculated (APROS code version 5.04) res...
The characteristics of the thermohydraulic solutions in APROS are considered for the nuclear power p...
APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Resea...
PACTEL facility has been used quite extensively for validation of the thermal hydraulic part of APRO...
The PACTEL is a test facility designed to model the thermal-hydraulic behaviours of the Soviet-desig...
APROS is a multifunctional simulator, suitable for various tasks throughout the complete power plant...
APROS (Advanced PROcess Simulator) is the computer simulation system for process and automation syst...
The European Commission fourth framework programme project ‘Assessment of passive safety injection s...
APROS code is a multifunctional process simulator which combines System Thermal-Hydraulic (STH) capa...
The paper describes the capabilities of APROS code in the simulation of the VVER-91 concept. The VVE...
The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to s...
APROS is the product being developed in the Process Simulators project of Imatran Voima Co. and Tech...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
VTT Energy, in co-operation with Lappeenranta University of Technology, has run experiments in the P...
The upper tie plate countercurrent flow limitation correlation of APROS was validated against experi...
This paper presents the comparison between the measured and calculated (APROS code version 5.04) res...
The characteristics of the thermohydraulic solutions in APROS are considered for the nuclear power p...