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Evaluation of Reactor Internals Integrity and Lifetime According to the NTD ASI

[+] Author Affiliations
Milan Brumovsky

UJV Rez, Rez, Czech Republic

Paper No. PVP2018-84140, pp. V01AT01A056; 5 pages
  • ASME 2018 Pressure Vessels and Piping Conference
  • Volume 1A: Codes and Standards
  • Prague, Czech Republic, July 15–20, 2018
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5158-6
  • Copyright © 2018 by ASME


Reactor internals are components that are no typical pressure boundary but they are nevertheless very important as they hold fuel elements and all reactor control system elements and thus must ensure their safe and reliable operation during the whole reactor life under all operating and even beyond bases regimes.

In principle, reactor internals can be replaced but their weight, quantity of very high activated material and cost such possibility practically excluded.

Thus, evaluation of the reactor internals condition and prediction of their behavior during the whole or even extended lifetime is of high importance. Reactor internals are subjected to very high neutron irradiation that could initiated not only stress corrosion (irradiation assisted) cracking but also large embrittlement and changes in dimensions (swelling and creep).

VERLIFE – “Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs during Operation” was initiated and co-ordinated by the Czech and was developed within the 5th Framework Program of the European Union in 2003 and later upgraded within the 6th Framework Program “COVERS – Safety of WWER NPPs” of the European Union in 2008. This Procedure had to fill the gap in original Soviet/Russian Codes and Rules for Nuclear Power Plants (NPPs) with WWER (Water-Water-Energetic-Reactor = PWR type) type reactors, as those codes were developed only for design and manufacture and were not changed since their second edition in 1989.

VERLIFE Procedure is based on these Russian codes but incorporates also new developments in research, mainly in fracture mechanics, and also some principal approaches used in PWR codes.

Within the last upgrading and principal extending of this VERLIFE Procedure was developed within the 3-years IAEA project (in close co-operation with another project of the 6th Framework Program of the European Union “NULIFE – Plant Life Management of NPPs”) that started in 2009 with final approval and editing in 2013”) a part dealing with the evaluation of reactor internals lifetime was elaborated..

This IAEA VERLIFE procedure for internals has been implemented into the existing Normative Technical Documentation (NTD) ASI (Czech Association of Mechanical Engineers), Section IV – Evaluation of Residual Lifetime of Components and Piping in WWER type NPPs.

Main damaging mechanisms that should be taken into account in reactor internals and the procedure are described in detail with necessary formulae for materials of internals:

- Radiation hardening

- Radiation embrittlement

- Radiation swelling

- Radiation creep

- Swelling under stress effect

- Swelling inducing embrittlement

- Irradiated assisted stress corrosion cracking

- Transformation austenite-ferrite

and also the method for evaluation of the resistance against non-ductile failure of postulated defect.

The paper will describe these main principles and also more detailed information on the procedure for evaluation of reactor internals will be given.

Copyright © 2018 by ASME



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