Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1980.MICROFICHE COPY AVAILABLE IN ARCHIVES AND ENGINEERING.Bibliography: leaf 31.by Susan M. Krolewski.B.S
The public has expressed concern about the safety of a nuclear power plant after the Fukushima Daiic...
Graduation date: 2002This research presents an analysis of thermal stratification in the reactor\ud ...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...
Cooling system in nuclear reactor is much influenced by counter-current flow. When a leakage is occu...
Counter-Current Flow Limitation (CCFL) is of importance for PWR safety analyses in several accident ...
Gas/liquid two-phase stratified flows in horizontal channels are frequently encountered in nuclear r...
During a postulated loss-of-coolant-accident (LOCA) in a pressurized water reactor (PWR) it is of vi...
For certain values of fluid velocity of two phases, a wave forms covering as well as blocking the ar...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor for th...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
A power limit criterion was developed for a postulated Loss of Pumping Accident (LOPA) in one of the...
In this paper, we report on the results using the BWR plant simulator about the plant behavior under...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
This paper concerns two independent safety investigations on critical and sub-critical heavy liquid ...
The public has expressed concern about the safety of a nuclear power plant after the Fukushima Daiic...
Graduation date: 2002This research presents an analysis of thermal stratification in the reactor\ud ...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...
Cooling system in nuclear reactor is much influenced by counter-current flow. When a leakage is occu...
Counter-Current Flow Limitation (CCFL) is of importance for PWR safety analyses in several accident ...
Gas/liquid two-phase stratified flows in horizontal channels are frequently encountered in nuclear r...
During a postulated loss-of-coolant-accident (LOCA) in a pressurized water reactor (PWR) it is of vi...
For certain values of fluid velocity of two phases, a wave forms covering as well as blocking the ar...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor for th...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
A power limit criterion was developed for a postulated Loss of Pumping Accident (LOPA) in one of the...
In this paper, we report on the results using the BWR plant simulator about the plant behavior under...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
This paper concerns two independent safety investigations on critical and sub-critical heavy liquid ...
The public has expressed concern about the safety of a nuclear power plant after the Fukushima Daiic...
Graduation date: 2002This research presents an analysis of thermal stratification in the reactor\ud ...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...