The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to simulate the real plant thermal-hydraulic transient of a Small Break Loss-Of-Coolant Accident (SBLOCA) of Loss-Of-Fluid Test (LOFT) facility. The LOFT is a scaled model of a Pressurized Water Reactor (PWR). This work is a part of a larger validation of the APROS thermal-hydraulic models. The results of SBLOCA transient calculated by APROS showed a reasonable agreement with the measured data
The Apros CONtainment model library (ACON) is an add-on product of the Apros ® (Advanced Process Si...
Great interest is given now to advanced nuclear reactors especially those using passive safety compo...
A small break loss-of-accident (SBLOCA) in a typical Babcock and Wilcox (B W) nuclear power plant wa...
The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to s...
The Loss-of-Fluid Test (LOFT) Facility is a scale model of a commercial PWR and is as fully function...
APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Resea...
The behavior of a VVER-440 nuclear power plant is simulated in postulated loss-of-feedwater accident...
The paper describes the capabilities of APROS code in the simulation of the VVER-91 concept. The VVE...
This thesis studied the performance of the thermal hydraulic software TRACE applied on an intermedia...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
The paper describes simulation of the Loviisa nuclear power plant ATWS-transients with APROS (Advanc...
A small-scale nonnuclear integral test facility designed to simulate a pressurized water reactor (PW...
The capability of the RELAP5-3D computer code to perform multi-dimensional analysis of a pressurized...
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...
The Apros CONtainment model library (ACON) is an add-on product of the Apros ® (Advanced Process Si...
Great interest is given now to advanced nuclear reactors especially those using passive safety compo...
A small break loss-of-accident (SBLOCA) in a typical Babcock and Wilcox (B W) nuclear power plant wa...
The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to s...
The Loss-of-Fluid Test (LOFT) Facility is a scale model of a commercial PWR and is as fully function...
APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Resea...
The behavior of a VVER-440 nuclear power plant is simulated in postulated loss-of-feedwater accident...
The paper describes the capabilities of APROS code in the simulation of the VVER-91 concept. The VVE...
This thesis studied the performance of the thermal hydraulic software TRACE applied on an intermedia...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
The paper describes simulation of the Loviisa nuclear power plant ATWS-transients with APROS (Advanc...
A small-scale nonnuclear integral test facility designed to simulate a pressurized water reactor (PW...
The capability of the RELAP5-3D computer code to perform multi-dimensional analysis of a pressurized...
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...
The Apros CONtainment model library (ACON) is an add-on product of the Apros ® (Advanced Process Si...
Great interest is given now to advanced nuclear reactors especially those using passive safety compo...
A small break loss-of-accident (SBLOCA) in a typical Babcock and Wilcox (B W) nuclear power plant wa...