This year, 7 different offers have been handed in for the fifth nuclear power unit of Finland. One of them is the VVER-91 plant concept of VVO Atomenergoexport (AEE). In cooperation with IVO International planning work has been made in order to fulfil the strict safety criteria of the Finnish authorities. Part of the accident analyses have been made by the Technical Research Centre of Finland (VTT). In Finland there is experience of the VVER type reactors. There are two VVER-440 reactors in Loviisa. A group of analyses made in VTT includes cases that belong to the class of Anticipated Transient Without Scram (ATWS). In this paper, methods and results of some loss of feedwater ATWS analyses are discussed
The licensing is a legal process to transfer the nuclear safety technology (developed and supported ...
The purpose of the work is to investigate the safety and reliability of the VVER-440 and LVR-15 reac...
The licensing is a legal process to transfer the nuclear safety technology (developed and supported ...
An European Conimunity sponsored Project focused on the subject ‘Accident Management (AIVI) in VVER-...
The fall of the Berlin wall and of the Soviet Union opened impressive perspectives for the research ...
VVER 1000 reactors have some unique and specific features (e.g. large primary and secondary side flu...
The research field focussing on the investigations and the analyses of severe accidents is an import...
The report provides a summary of the publicly funded nuclear reactor safety research project "Severe...
The paper describes the capabilities of APROS code in the simulation of the VVER-91 concept. The VVE...
A number of transient and accident analysis codes have been developed in Finland during the past twe...
A three-dimensional reactor dynamics computer code has been developed, validated and applied for tra...
This paper describes the results of an analysis of loss of coolant accidents (LOCA`s) for the Soviet...
The OECD/NEA PSB-VVER project provided unique and useful experimental data from the large-scale PSB-...
International audienceWithin the framework of the French 4th-generation Sodium-cooled Fast Reactor s...
The present paper deals with the investigation study on accident management in VVER-1000 reactor typ...
The licensing is a legal process to transfer the nuclear safety technology (developed and supported ...
The purpose of the work is to investigate the safety and reliability of the VVER-440 and LVR-15 reac...
The licensing is a legal process to transfer the nuclear safety technology (developed and supported ...
An European Conimunity sponsored Project focused on the subject ‘Accident Management (AIVI) in VVER-...
The fall of the Berlin wall and of the Soviet Union opened impressive perspectives for the research ...
VVER 1000 reactors have some unique and specific features (e.g. large primary and secondary side flu...
The research field focussing on the investigations and the analyses of severe accidents is an import...
The report provides a summary of the publicly funded nuclear reactor safety research project "Severe...
The paper describes the capabilities of APROS code in the simulation of the VVER-91 concept. The VVE...
A number of transient and accident analysis codes have been developed in Finland during the past twe...
A three-dimensional reactor dynamics computer code has been developed, validated and applied for tra...
This paper describes the results of an analysis of loss of coolant accidents (LOCA`s) for the Soviet...
The OECD/NEA PSB-VVER project provided unique and useful experimental data from the large-scale PSB-...
International audienceWithin the framework of the French 4th-generation Sodium-cooled Fast Reactor s...
The present paper deals with the investigation study on accident management in VVER-1000 reactor typ...
The licensing is a legal process to transfer the nuclear safety technology (developed and supported ...
The purpose of the work is to investigate the safety and reliability of the VVER-440 and LVR-15 reac...
The licensing is a legal process to transfer the nuclear safety technology (developed and supported ...