After the Chernoby1 accident, occurred in the graphite moderated boiling light water cooled reactor (RBMK reactor) built in former USSR, Japan has offered technological support for improving the safety of the same type of reactor. For instance, the reactor coolant leak detection system developed for ATR, which uses a high-temperature-resistant microphone, was provided with the Leningrad Nuclear Power Plant in Russia. The RBMK reactor is a pressure tube type reactor like Fugen, but it differs in the respect that it uses graphite as moderator. The structure of its reactor cooling system is similar to Fugen, so the safety improvement technology developed for ATR could be applied to the RBMK reactor as well.
For the Ignalia Nuclear Power Plant in Lithuania, Japan offered technological support including water chemistry and water level control support system for operational training, as measures against corrosion of pressure tubes and problems in water level control in the steam drum at the point of low power. To cope with the corrosion of pressure tubes, a plant data server system necessary to collect operational and water chemistry data, and a water quality analyzer were supplied, and supporting activities regarding data analysis, investigation into the degree of corrosion, analytical evaluation, etc. were performed. In addition, we installed JNC-developed equipment for measuring the thickness of oxide layer on the pressure tube, which made possible to evaluate the degree of corrosion without drawing out the pressure tube. This development considerably improved the inspection quality of pressure tube integrity. For the water level control, an operational support system based on fuzzy feedwater control technology was provided to serve as an operator training system for the operational safety improvement.
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