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ATLAS-2 was a follow-up to phase one and was focused on topics of high safety relevance for both existing and future nuclear power plants that had been identified by the participants. The following topics were addressed:
long-term coolability with partial core blockage
passive core makeup during station blackout (SBO) and small break loss of coolant accident (SBLOCA)
intermediate break loss of coolant accident (IBLOCA), including risk-informed break size definition
design extension condition (DEC) scenarios such as steam line break (SLB) followed by steam generator tube rupture (SGTR) and shutdown coolability without residual heat removal system (RHRS)
open test to address scaling issues by performing counterpart test to previous Integral Effects Tests (IETs).
The experimental programme was designed to provide an integral-effect experimental database to support the enhancement of code predictive capability and accuracy of models. In phase 2, a total of 8 tests were performed. Analytical activities were pursued including the oganisation of a joint workshop with the OECD/NEA PKL4 project which outcomes are provided here.
The summary report of phase 2 is available here.
Participating countries: Belgium, China, Czech Republic, France, Germany, Korea, Spain, Switzerland, United Arab Emirates and the United States.
Project period: October 2017 - September 2020
The distribution of this package is restricted and subject to prior approval.
For more detailed information visit the ATLAS Project.
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Keywords: accident analysis, loop, simulation, thermal hydraulics.