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|Title:||Tacis Projects for VVER Reactor Pressure Vessel Embrittlement|
|Other Contributors:||AHLSTRAND RALF|
|Citation:||Proceedings of the 9th International Conference Material Issues in Design, Manufacturing and Operation of Nuclear Power Plants Equipment|
|Type:||Contributions to Conferences|
|Abstract:||The European Union' TACIS programme was established to support the New Independent States since 1991. One priority for TACIS funding is nuclear safety. For TACIS, the European Commission (EC); Directorate General External Relations is responsible for the Indicative Programmes; whilst the EC-EuropeAid Co-operation Office is in charge of identifying and implementing all the assistance projects through the Annual Programmes. In these programmes, EC-Joint Research Center (JRC) is the Technical & Scientific adviser of above mentioned EC Directorates. During the years of Tacis assistance activities in nuclear safety quite a few programs were dedicated to the Reactor Pressure Vessel (RPV) embrittlement issue. The ageing of the RPV was of special concern due to the faster than expected neutron irradiation embrittlement of the core region weld of the VVER 440 NPPs and some shortcomings of the RPV surveillance program in VVER 1000 NPPs. Most of the Tacis ageing projects were so far dedicated to studying the RPV embrittelement and integrity issue. In this paper objectives, implementation and results of the following completed Tacis projects on the RPV embrittlement issue are briefly described: 1. Tacis R1.1/91, Reactor Vessel embrittlement; 2. Tacis R2.02/95, VVER 440/V-230 Reactor Pressure Vessel Integrity Assessment; 3. Tacis R2.06/96, Surveillance program for VVER 1000 RPV “ 4. Tacis SRR2/95, Development of Advanced methods for evaluation of Irradiation Embrittlement of VVER 1000/320 type RPVs” The situation regarding the ongoing Tareg 2.01/00 project “Validation of neutron embrittlement for VVER 1000 & VVER 440 RPVs, with emphasis on integrity assessment and the its twin project Tareg 2.01/03 Neutron irradiation embrittlement assessment and validation of embrittlement models for VVER Reactor pressure vessels are also briefly presented.|
|JRC Institute:||Institute for Energy and Transport|
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