Numerical analysis of MYRRHA inter-wrapper flow experiment at KALLA
Creators
- 1. Karlsruhe Institute of Technology, Karlsruhe (Germany). AREVA Nuclear Professional School
Description
The MYRRHA reactor, which is developed at SCK-SCN in Belgium, represents a multi-purpose irradiation facility. Its prominent feature is a pool design with the nuclear core submerged in liquid metal lead bismuth. During transients between normal operation and accident conditions decay heat removal is ensured by forced and natural convection, respectively. The flow in the gap between the fuel assemblies plays an important role in limiting maximum temperatures which should not be exceeded to avoid core damage. Due to the scarce database, within the Horizon 2020 - research and innovation framework program of the EU, the SESAME project was established to develop and validate advanced numerical approaches, to achieve a new or extended validation base and to establish best practice guidelines including verification and validation and uncertainty quantification. In particular the current work supports the inter-wrapper flow experiment at KALLA.
Additional details
Publishing Information
- Journal Title
- Atw. Internationale Zeitschrift fuer Kernenergie
- Journal Volume
- 63
- Journal Issue
- 4
- Journal Page Range
- p. 226-229
- ISSN
- 1431-5254
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 49054257
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONVECTION; FLOW MODELS; FLOW RATE; FLUID FLOW; FUEL ELEMENT CLUSTERS; MYRRHA FACILITY; VALIDATION
- Descriptors DEC
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FUEL ASSEMBLIES; HEAT TRANSFER; MASS TRANSFER; MATHEMATICAL MODELS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SUBCRITICAL ASSEMBLIES; TESTING