Objective
Kola Nuclear Power Plant is located in the Arctic area of Russia near the town of Polaner Sorry. The key component of NPP is the Reactor Pressure Vessel (RPV). The evaluation and prognosis of RPV ernbrittlement and the allowable period of its safe operation are performed on the basis of impact test results on irradiated surveillance specimens (SS) . However the results of SS testing are not fully representative. The key issue is the difference between the irradiation temperature of the SS and the actual RPV component temperature. The main OBJECTIVE of this project is: The consolidation of Western and Eastern scientific and technological practice to implement modern methods for SS irradiation temperature measurement in order to improve the reliability of RPV ernbrittlement prediction.
Topic(s)
Data not availableCall for proposal
Data not availableFunding Scheme
CSC - Cost-sharing contractsCoordinator
28709 SAN SEBASTIAN DE LOS REYES - MADRID
Spain