Objective
The present project was intended as an extension of the work performed in the TACIS 91-3.5.-Maintenance Project.
Navigation path
Objective
The present project was intended as an extension of the work performed in the TACIS 91-3.5.-Maintenance Project.
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The objective of the present project was to perform a limited integrity assessment of the VVER 1000 Reactor Pressure Vessel (RPV) taking into account the irradiation embrittlement effect.
The project covered four major areas:
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The objective of the project was to analyse the current leak rate of the confinement for VVER-230 reactors and consequently to propose how to decrease it drastically.
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The original design of WWER reactors did not include a diagnostic system in order to monitor the potential danger to the integrity of reactor coolant system (RCS) and to provide an early warning of RCS pressure boundary developing defects.
Part A. Development of Accident management procedures on the test facility PSB-VVER-1000 at Electrogorsk
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With this project training on NDT equipment should be given.
The equipment’s origin was Intercontrole, France. (The NDT-equipment for which the training was performed, has been financed from other than Tacis funding).
Result
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The objective of this project consisted of 3 tasks
Task 1: Vent Stack Radioactive Release Measurement Upgrade
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This project on Reactor Vessel embrittlement was identified in the very early stage (1991) of the TACIS and PHARE programmes for nuclear safety as a main topic.
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The objective of the project was to develop a residual life time diagnostic system based both on existing Russian developments and on the Contractor’s experience. This system was to be implemented on operating VVER-NPPs.
Result
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