The main goal of this Certification is to summarize all available important information and experience on base and weld materials for WWER-440 reactor pressure vessels (RPV) on the basis for Knowledge Management in other countries and Preservation/Dissemination. The first of all the Report summarizes data which was received in Soviet Union (later Russia) and Czech Republic as the main countries which had produced this type of RPV. The book summarizes historical basis for the choice of materials, main principles of RPV design and manufacturing as well as results from Qualification Test Programmes, statistical evaluation of test results from individual type of semi-products/welds and final vessels. Information on defects/repair of semi-produc...
A joint pressure vessel integrity research programme involving three partners is being carried out d...
The efficiency of fracture toughness determined by the methodology of normative document PNAE G-7-00...
A study investigating the WWER-440/213 RPV cladding properties and their degradation due to neutron ...
The cataloguing and revision of reactor pressure vessels (RPV) manufacturing and in-service inspecti...
The JRC-IE effort towards Preservation and Knowledge Management in the specific field of RPV embritt...
The surveillance test results of the reactor pressure vessels (RPV) of three Russian WWER-1000 type ...
The investigation of reactor pressure vessel (RPV) material from the decommissioned Greifswald nucle...
The cataloguing and revision of reactor pressure vessels (RPV) manufacturing and in-service inspecti...
Prediction of irradiation embrittlement of Reactor Pressure Vessel (RPV) materials is performed usua...
This master‘s thesis deals with radiation damage of reactor pressure vessels, specifically of NPP Du...
This paper describes part of a knowledge preservation programme coordinated by JRC Petten. The follo...
It is known that for Russian-type and Western water reactor pressure vessel steels there is a simila...
This paper presents the capabilities of International Database for the precise and comprehensive of ...
This paper is illustrating the potential of the well-known low alloyed clean steels, extensively use...
Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power...
A joint pressure vessel integrity research programme involving three partners is being carried out d...
The efficiency of fracture toughness determined by the methodology of normative document PNAE G-7-00...
A study investigating the WWER-440/213 RPV cladding properties and their degradation due to neutron ...
The cataloguing and revision of reactor pressure vessels (RPV) manufacturing and in-service inspecti...
The JRC-IE effort towards Preservation and Knowledge Management in the specific field of RPV embritt...
The surveillance test results of the reactor pressure vessels (RPV) of three Russian WWER-1000 type ...
The investigation of reactor pressure vessel (RPV) material from the decommissioned Greifswald nucle...
The cataloguing and revision of reactor pressure vessels (RPV) manufacturing and in-service inspecti...
Prediction of irradiation embrittlement of Reactor Pressure Vessel (RPV) materials is performed usua...
This master‘s thesis deals with radiation damage of reactor pressure vessels, specifically of NPP Du...
This paper describes part of a knowledge preservation programme coordinated by JRC Petten. The follo...
It is known that for Russian-type and Western water reactor pressure vessel steels there is a simila...
This paper presents the capabilities of International Database for the precise and comprehensive of ...
This paper is illustrating the potential of the well-known low alloyed clean steels, extensively use...
Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power...
A joint pressure vessel integrity research programme involving three partners is being carried out d...
The efficiency of fracture toughness determined by the methodology of normative document PNAE G-7-00...
A study investigating the WWER-440/213 RPV cladding properties and their degradation due to neutron ...