Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1961.Vita.Includes bibliographical references (leaves 202-207).by Helge Christensen.Ph.D
The possible failure of an Emergency Core Cooling System (ECCS) train due to a large amount of entra...
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1986.Series from...
An experimental study on flooding with steam and water in a large diameter vertical tube was conduct...
Variations in the distribution of steam bubble, the "void" distribution, in a boiling channel as a f...
Introduction: Knowledge of the pressure drop in a channel and the resulting flow redistribution is e...
The problem of determining the dynamic properties of the steam void fraction undergoing random varia...
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997.Includes b...
Fundamental work on heat removal by bubble formation and by increased heat diffusivity as a result o...
"June 1961"Bibliography: p. 58-59.Operated by the University of Chicago underMode of access: Interne...
Gas-liquid two-phase flows occur in a range of chemical, process, petroleum, metallurgical and power...
Following a loss of coolant accident in a nuclear reactor, the materials of the core can crumble and...
International audienceFollowing a loss of coolant accident in a nuclear reactor, the materials of th...
The focus in this thesis is to improve knowledge of the BWR related uncertainties void, channel bow,...
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.MICROFICHE...
AbstractThe void fraction profile in a boiling channel is essential in analyzing convective flow boi...
The possible failure of an Emergency Core Cooling System (ECCS) train due to a large amount of entra...
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1986.Series from...
An experimental study on flooding with steam and water in a large diameter vertical tube was conduct...
Variations in the distribution of steam bubble, the "void" distribution, in a boiling channel as a f...
Introduction: Knowledge of the pressure drop in a channel and the resulting flow redistribution is e...
The problem of determining the dynamic properties of the steam void fraction undergoing random varia...
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997.Includes b...
Fundamental work on heat removal by bubble formation and by increased heat diffusivity as a result o...
"June 1961"Bibliography: p. 58-59.Operated by the University of Chicago underMode of access: Interne...
Gas-liquid two-phase flows occur in a range of chemical, process, petroleum, metallurgical and power...
Following a loss of coolant accident in a nuclear reactor, the materials of the core can crumble and...
International audienceFollowing a loss of coolant accident in a nuclear reactor, the materials of th...
The focus in this thesis is to improve knowledge of the BWR related uncertainties void, channel bow,...
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.MICROFICHE...
AbstractThe void fraction profile in a boiling channel is essential in analyzing convective flow boi...
The possible failure of an Emergency Core Cooling System (ECCS) train due to a large amount of entra...
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1986.Series from...
An experimental study on flooding with steam and water in a large diameter vertical tube was conduct...
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