Zobrazeno 1 - 10
of 58
pro vyhledávání: '"K. Litfin"'
Publikováno v:
Nuclear Engineering and Design. 330:225-240
Internal blockages in fuel rod bundles can be rather small and may have a negligible global effect on the flow rate in a fuel assembly, and yet they can still produce significant local hot spots potentially leading to clad failure. Within the Europea
Publikováno v:
Nuclear Engineering and Design. 301:111-127
An experimental campaign considering a 19-pin hexagonal rod bundle with wire spacers, cooled by forced-convective LBE was completed at the Karlsruhe Liquid Metal Laboratory (KALLA). In the frame of the European research project SEARCH (Safe Exploitat
Publikováno v:
Nuclear Engineering and Design. 371:110928
Autor:
Djamel Lakehal, K. Litfin, K. Van Tichelen, Siju Thomas, G. Losi, Diego Angeli, Vincent Moreau, Abdalla Batta, A. G. Class, Luca Massidda, Kyle G. Mooney, Thomas Wetzel
Publikováno v:
Nuclear Engineering and Design. 290:107-118
Accelerator Driven Systems (ADS) are extensively investigated for the transmutation of high-level nuclear waste within many worldwide research programs. The first advanced design of an ADS system is currently developed in SCK•CEN, Mol, Belgium: the
Autor:
A. Batta, H. Doolaard, K. Litfin, Andreas G. Class, Sandro Manservisi, M. Viellieber, F. Menghini, Michael Böttcher, Ferry Roelofs, J. Pacio
Publikováno v:
Nuclear Engineering and Design. 290:27-39
Thermal-hydraulics is a key scientific subject to be investigated for the development of innovative reactor systems. For applications using liquid metals as coolants this task is particularly challenging due to their very low Prandtl number (Pr), pre
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 305:795-802
A prototype of a heavy liquid metal free surface target as proposed for the multi-purpose hybrid research reactor for high-tech applications in Mol, Belgium, has been set up and experimentally investigated at the Karlsruhe Liquid Metal Laboratory. A
Autor:
K. Litfin, F. Fellmoser, Robert Stieglitz, M. Daubner, Th. Wetzel, Luca Marocco, J. Pacio, Simon Taufall
Publikováno v:
Nuclear Engineering and Design. 273:33-46
Heavy-liquid metals, such as lead and lead-bismuth eutectic (LBE), are prominent candidate coolants for advanced fast reactor concepts and accelerator-driven systems. The thermal-hydraulic behavior of these fluids in fuel-assembly-representative geom
Autor:
Thomas Wetzel, K. Litfin, Carsten Schroer, Jürgen Konys, Wolfgang Hering, L. Stoppel, Georg Müller, Luca Marocco, Robert Stieglitz, Annette Heinzel, J. Pacio, Alfons Weisenburger
Liquid metals appear to be attractive heat-transport fluids, in particular if looking at their high thermal conductivities and low viscosities. Despite some pioneering technical applications in the past, complex handling, special requirements, safety
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6e0bef3a0ad35f4b817f580e400cd6e2
http://hdl.handle.net/11311/1030274
http://hdl.handle.net/11311/1030274
Publikováno v:
Journal of Nuclear Materials. 415:425-432
In the framework of accelerator driven sub-critical reactor systems heavy liquid metals are considered as coolant for the reactor core and the spallation target. In particular lead or lead bismuth eutectic (LBE) exhibit efficient heat removal propert
Publikováno v:
Nuclear Engineering and Design. 240:1830-1842
The aim of this paper is to correlate experimentally measured pressure drop data across grid spacers to the set of correlations proposed by Rehme, based on the experiments performed in a water loop at the Scalbatraio Laboratory of Pisa University (20