0

Full Content is available to subscribers

Subscribe/Learn More  >

Implementation of Small Punch Testing and Automated Ball Indentation in the Process of Irradiated NPP Materials Degradation Evaluation

[+] Author Affiliations
Radim Kopriva, Ivana Eliasova, Milos Kytka

UJV Rez, a. s., Husinec, Czech Republic

Paper No. ICONE24-60620, pp. V005T15A043; 5 pages
doi:10.1115/ICONE24-60620
From:
  • 2016 24th International Conference on Nuclear Engineering
  • Volume 5: Student Paper Competition
  • Charlotte, North Carolina, USA, June 26–30, 2016
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5005-3
  • Copyright © 2016 by ASME

abstract

In the terms of nuclear power plant operational life management, current trend of components lifetime extension requires precise and credible information of structural material degradation. Present-day standard conventional methods of mechanical testing are usually based on the use of large specimens and higher consumption of testing material, whose availability and volume is often limited.

For determination of material properties, sampling of the necessary volume of material is in most cases connected with affecting the integrity or even destruction of the assessed component. Moreover, several components are not usually covered surveillance programs, e.g. reactor pressure vessel internals.

Innovative testing methods of Small Punch Testing (SPT) and Automated Ball Indentation Test (ABIT) are based on the determination of material properties from miniaturized testing specimens and their semi-destructive approach is very promising for the possibility of present data base of irradiated materials testing results enlargement and enable the option of component in-situ testing (ABI testing).

Paper describes the process of implementation of Small Punch Testing and Automated Ball Indentation Testing techniques in the evaluation of mechanical properties of irradiated NPP structural materials degradation. Presentation depicts all necessary steps carried out at the Hot Cell facility of UJV Rez, a. s. (Integrity and Technical Engineering Division) for the employment of these innovative testing techniques to the portfolio of accredited mechanical tests performed within the frame of surveillance programs of WWER type reactors — e.g. preliminary design, modification of the testing equipment, fractography analyses etc.

Detailed comparison between the results of standard conventional testing techniques and SPT and ABIT for both initial unirradiated and irradiated state for the material A533B (JRQ) is included for determination of suitability of used methods for testing of materials within the surveillance programs of WWER type reactors.

Copyright © 2016 by ASME

Figures

Tables

Interactive Graphics

Video

Country-Specific Mortality and Growth Failure in Infancy and Yound Children and Association With Material Stature

Use interactive graphics and maps to view and sort country-specific infant and early dhildhood mortality and growth failure data and their association with maternal

NOTE:
Citing articles are presented as examples only. In non-demo SCM6 implementation, integration with CrossRef’s "Cited By" API will populate this tab (http://www.crossref.org/citedby.html).

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In