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Review of Experimental Database to Support Nuclear Power Plant Safety Analyses in SGTR and LOCA Domains

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

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 include 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.

Keywords: Loss-of-Coolant Accident (LOCA); Steam Generator Tube Rupture (SGTR)

Permalink: https://www.hzdr.de/publications/Publ-37228


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