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Consolidation of scientific technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant

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)

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Call for proposal

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Coordinator

TECNATOM S.A.
Address
1,avenida Montes De Oca 1
28709 San Sebastian De Los Reyes - Madrid
Spain

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Participants (4)

ARMATOM
Armenia
Address
Admiral Isakov Prospect 50
375114 Yerevan

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KFKI - ATOMIC ENERGY RESEARCH INSTITUTE - HUNGARIAN ACADEMY OF SCIENCES
Hungary
Address
Konkoly-thege Miklos Ut 29-33
1121 Budapest

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KOLA NUCLEAR POWER PLANT
Russia
Address
Polyarnye Zori
184151 Murmansk Region

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RUSSIAN RESEARCH CENTRE 'KURCHATOV INSTITUTE '
Russia
Address
Kurchatov Square 1
123182 Moscow

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