Add to ORKGOriginally presented as the first author's thesis, (Sc. D.)--in the M.I.T. Dept. of Nuclear Engineering, 1977Includes bibliographical reference
The safety assessment of nuclear power plants requires the consideration of the several physical phe...
The accuracy requirements for modern nuclear reactor simulation are steadily increasing due to the c...
This chapter briefly describes the fundamental concepts of heat transfer and hydraulic resistance in...
Thesis: Sc. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1977Includ...
The thermal hydraulic analysis of nuclear reactors is largely performed by what are known as system...
Several improvements have been made to COBRA-IIIC/MIT. All of the improvements, except for one, have...
Due to the condition of the original material, there are unavoidable flaws in this reproduction. We ...
The nuclear industry has a long history of usage of reliable and well-validated software for design ...
A computational fluid dynamics code is used to model the primary natural circulation loop of a propo...
The difficulty in predicting locally and globally the transient evolution of two-phase or multiphase...
Graduation date: 1986COBRA-OSU computer code is a fast running computer code for coupled Kinetic-The...
The ability to accurately predict local pin powers in nuclear reactors is necessary to understand th...
The Numerical Nuclear Reactor (NNR) was developed to provide a high-fidelity tool for light water r...
The difficulty in predicting locally and globally the transient evolution of two-phase or multiphase...
Le calcul d'écoulements dans les générateurs de vapeur des réacteurs à eau pressurisée est un problè...
The safety assessment of nuclear power plants requires the consideration of the several physical phe...
The accuracy requirements for modern nuclear reactor simulation are steadily increasing due to the c...
This chapter briefly describes the fundamental concepts of heat transfer and hydraulic resistance in...
Thesis: Sc. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1977Includ...
The thermal hydraulic analysis of nuclear reactors is largely performed by what are known as system...
Several improvements have been made to COBRA-IIIC/MIT. All of the improvements, except for one, have...
Due to the condition of the original material, there are unavoidable flaws in this reproduction. We ...
The nuclear industry has a long history of usage of reliable and well-validated software for design ...
A computational fluid dynamics code is used to model the primary natural circulation loop of a propo...
The difficulty in predicting locally and globally the transient evolution of two-phase or multiphase...
Graduation date: 1986COBRA-OSU computer code is a fast running computer code for coupled Kinetic-The...
The ability to accurately predict local pin powers in nuclear reactors is necessary to understand th...
The Numerical Nuclear Reactor (NNR) was developed to provide a high-fidelity tool for light water r...
The difficulty in predicting locally and globally the transient evolution of two-phase or multiphase...
Le calcul d'écoulements dans les générateurs de vapeur des réacteurs à eau pressurisée est un problè...
The safety assessment of nuclear power plants requires the consideration of the several physical phe...
The accuracy requirements for modern nuclear reactor simulation are steadily increasing due to the c...
This chapter briefly describes the fundamental concepts of heat transfer and hydraulic resistance in...