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 von Mori, Takamasa, Cigarini, Marco, Dalle Donne, Mario

Conceptual design of two helium cooled fusion blankets (ceramic and liquid breeder) for INTOR von Dalle Donne, Mario

A parametric thermohydraulic study of an advanced pressurized light water reactor with a tight fuel rod lattice von Dalle Donne, Mario

European GCFR Program Plans von Dalle Donne, Mario, Wirtz, K.

Beryllium irradiation embrittlement test (BSBE) programme assessment of the tensile and fracture toughness test data von Harries, Donald Rees, Dalle Donne, Mario, Scaffidi-Argentina, Francesco

Beryllium irradiation embrittlement test programme material and specimen specification, manufacture and qualification von Harries, Donald Rees, Dalle Donne, Mario

CHF-KFK-3: a critical heat flux correlation for triangular arrays of rods with tight lattices von Dalle Donne, Mario

Pre-test calculation of reflooding experiments with wider lattice in APWR-geometry (FLORESTAN 2) using the advanced computer code FLUT-FDWR von Mori, Takamasa, Cigarini, Marco, Dalle Donne, Mario

HADA von Dalle Donne, Mario

Some considerations on tritium control in a helium cooled ceramic blanket for the NET reactor von Dalle Donne, Mario

Heat transfer for turbulent flow of helium or hydrogen in a tube at high temperatures von Dalle Donne, Mario

Wärmeübergang von rauhen Oberflächen von Dalle Donne, Mario

Inhaltsverzeichnis

Beryllium irradiation embrittlement test (BSBE) programme assessment of the tensile and fracture toughness test data von Harries, Donald Rees, Dalle Donne, Mario, Scaffidi-Argentina, Francesco

CHF-KFK-3 a critical heat flux correlation for triangular arrays of rods with tight lattices von Dalle Donne, Mario

Evaluation of forced reflooding experiments using the FLUT-FDWR-MM (modified version of FLUT-FDWR with Moving Mesh in Heat Conductor Model) von Mori, Takasama, Cigarini, Marco, Dalle Donne, Mario

Parametric thermohydraulic calculations for advanced pressurized water reactors with the code HADA-2 von Cigarini, Marco, Dalle Donne, Mario

A critical heat flux correlation for advanced pressurized light water reactor application von Dalle Donne, Mario

A new and simple method of estimating the liquid superheat due to surface conditions in nucleate boiling and its application to Sodium von Dalle Donne, Mario, Stegemann, D., Väth, W.

IEA implementing agreement for a programme of research and development on fusion materials

Weitere Verfasser: “… Dalle Donne, Mario …”

European helium cooled pebble bed (HCPB) test blanket ITER design description document status 1.12.1996

Weitere Verfasser: “… Dalle Donne, Mario …”