Objective
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.
Navigation path
Objective
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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The objective of this project consisted of 3 tasks
Task 1: Vent Stack Radioactive Release Measurement Upgrade
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The primary objectives of this project were:
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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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The objective of the project was to study whether the LBB concept can be applied to the piping system of VVER 440/230 and to assess the possibility to achieve, under certain conditions, a high reliability level. More precisely, it was analysed:
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