Topical day - Ageing of reactor pressure vessel materials

Research output: Report/book › BLG - Open report

Authors

Institutes & Expert groups

Documents & links

Documents

  • BLG-807

    Final published version, 943 KB, PDF document

Details

Original languageEnglish
Place of PublicationMol, Belgium
PublisherStudiecentrum voor Kernenergie
Number of pages13
Publication statusPublished - 1999

Publication series

NameSCK•CEN Reports
PublisherStudiecentrum voor Kernenergie
No.BLG-807

Related by author

  1. On the use of miniaturized ct specimens for fracture toughness characterization of RPV materials: PVP2016-63607

    Research output: Contribution to report/book/conference proceedings › In-proceedings paper › peer-review

  2. Characterisation of the fracture properties in the ductile to brittle transition region of the weld material of a reactor pressure vessel

    Research output: Contribution to journal › Article › peer-review

  3. Structural integrity assessment of a nuclear vessel with FITNET FFS and Master Curve approach

    Research output: Contribution to journal › Article › peer-review

  4. Validation and application of the Master Curve and reconstitution techniques to a Spanish nuclear vessel

    Research output: Contribution to journal › Article › peer-review

  5. Status and Perspectives of Nuclear Reactor Pressure Vessel Life Extension up to 60 Years Operation in Belgium

    Research output: Report/book › BLG - Open report › peer-review

ID: 1054955