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Nuclear PWR Plants: Managing the Expertises of Cast Components Removed From Reactor Coolant Circuit

[+] Author Affiliations
Georges Bezdikian

Georges Bezdikian Consulting, Le Vesinet, France

Paper No. PVP2008-61551, pp. 89-98; 10 pages
doi:10.1115/PVP2008-61551
From:
  • ASME 2008 Pressure Vessels and Piping Conference
  • Volume 7: Operations, Applications and Components
  • Chicago, Illinois, USA, July 27–31, 2008
  • Conference Sponsors: Pressure Vessels and Piping
  • ISBN: 978-0-7918-4830-2 | eISBN: 0-7918-3828-5
  • Copyright © 2008 by ASME

abstract

The French utility has organized the aging degradation assessment for nuclear plants in operation in maximum safety rules. Also the utility decided to engaged large program of expertises, for each degradations identified, based on research and development activities and prediction criteria program of Nuclear Plants in function of several actions: expertises, data bases on characteristics, etc. This paper shows the expertise results and thermal aging for cast duplex stainless steel studies on reactor coolant circuit components engaged to evaluate and to monitor the toughness evaluation and increasing factor. Also this paper presents the strategy associated. This paper shows the applications were evolved for 3-loop PWR plants. The monitoring was mainly oriented on evaluation of the ratio computation and measurement. This integrity assessment and expertises results values available periodically were performed considering: • the life evaluation of the plants and alternative maintenance actions, • the large database from cast reactor coolant component assessed after removed from nuclear power plants, • the identification of degradation for different components and prediction criteria proposed. The results obtained are updated in the periodic maintenance program and in volume of expertise database for life management.

Copyright © 2008 by ASME

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