Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains

Z. Hózer (Corresponding Author), M. Adorni, A. Arkoma, V. Busser, B. Bürger, K. Dieschbourg, R. Farkas, N. Girault, L. E. Herranz, R. Iglesias, M. Jobst, A. Kecek, C. Leclere, R. Lishchuk, M. Massone, N. Müllner, S. Sholomitsky, E. Slonszki, P. Szabó, T. TaurinesR. Zimmerl

Research output: Contribution to journalReview Articlepeer-review

3 Citations (Scopus)

Abstract

In the framework of the EU R2CA project the available experimental databases were reviewed to support nuclear power plant safety analyses in SGTR and LOCA domains. The review focused on the phenomena related to fuel failure, fission products release from the fuel rods and activity transport up to the environment. Furthermore, it was shown that the phenomena were covered by different scale facilities and different experimental procedures for several reactor designs and materials. Among the tests several separate effect tests and integral tests are listed and some NPP measurements were also included. It was concluded that the reviewed database, which includes more than forty experimental programmes and measurement series can be considered as a reliable basis to support the development and validation of numerical models for SGTR and LOCA safety analyses.

Original languageEnglish
Article number110001
Number of pages12
JournalAnnals of Nuclear Energy
Volume193
DOIs
Publication statusPublished - Dec 2023
MoE publication typeA2 Review article in a scientific journal

Keywords

  • Activity release
  • Activity transport
  • Fuel failure
  • Loss-of-coolant accident (LOCA)
  • Steam generator tube rupture (SGTR)

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