Dalle Donne, Mario.
Donne, M. Dalle
VIAF ID: 44129958 ( Personal )
Permalink: http://viaf.org/viaf/44129958
Preferred Forms
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- 100 1 _ ‡a Dalle Donne, Mario
- 100 1 _ ‡a Dalle Donne, Mario
- 100 1 _ ‡a Dalle Donne, Mario
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4xx's: Alternate Name Forms (6)
Works
Title | Sources |
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Beryllium irradiation embrittlement test programme material and specimen specification, manufacture and qualification | |
CHF-KFK-3: a critical heat correlation for triangular arrays of rods with tight lattices | |
Conceptual design of two helium cooled fusion blankets (ceramic and liquid breeder) for INTOR | |
Convective heat transfer from rough surfaces with two-dimensional ribs, transitional and laminar flow | |
EIR, KfK joint heat transfer experiment on a single rod, roughened with trapezoidal rounded ribs and cooled by various gases | |
European DEMO BOT solid breeder blanket | |
European GCFR program plans | |
European helium cooled pebble bed (HCPB) test blanket ITER design description document | |
Evaluation of forced reflooding experiments using the FLUT-FDWR-MM (modified version of FLUT-FDWR with moving mesh in heat conductor model) | |
Gas cooled fast reactor background, facilities, industries and programmes | |
HADA 2 (modified version of HADA) a FORTRAN IV program for the thermohydraulic design of an advanced pressurized light water reactor with a tight fuel rod lattice | |
Heat transfer and friction coefficients for air flow in a smooth annulus results of a recent experiment and comparison with previous correlations | |
High temperature heat transfer | |
IEA implementing agreement for a programme of research and development on fusion materials | |
Kernforschungszentrum Karlsruhe | |
Laboratory studies of the meltfront propagation in a borax core-catcher | |
Measurements of density and of thermal expansion coefficient of sodium tetraborate (borax) UO2 and of sodium metaborate-UO2 solutions | |
Pre-test calculation of reflooding experiments with wider lattice in APWR-geometry (FLORESTAN 2) using the advanced computer code FLUT-FDWR | |
Problematik eines Core-Catchers für einen gasgekühlten Schnellen Brüter | |
Some considerations on the development of a core catcher of a gas cooled fast reactor | |
Some considerations on tritium control in a helium cooled ceramic blanket for the NET reactor | |
Status of beryllium development for fusion applications, 1994: | |
Status report KfK contribution to the development of DEMO-relevant test blankets for NET-ITER | |
Temperature and heat-flux distribution in the molten core mass of a GCFR after a hypothetical melt-down accident paper presented at the Specialist Meeting on GCFR Safety, NEA Coordinating Group on GCFR Development, Brussels 29, 30 nov. 1972 | |
Wärmeübergang von rauhen Oberflächen | |
Wymiana ciepła w reaktorach przy wysokich temperaturach |