Ex-vessel core catcher cooling system driven by natural circulation is designed using a full scaled air-water system. A transparent half symmetric section of a core catcher coolant channel of a pressurized water reactor was designed with instrumentations for local void fraction measurement and flow visualization. Two designs of air-water top separator water tanks are studied including one with modified ��super-step�� design which prevents gas entrainment into down-comer. In the experiment air flow rates are set corresponding to steam generation rate for given corium decay power. Measurements of natural circulation flow rate, spatial local void fraction distribution and re-wetting time near the top wall are carried out for various air flow r...
The full text of this article will not be available in ULIR until the embargo expires on the 08/02/2...
Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-s...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
DoctorPassive cooling based on natural circulation is utilized in core catcher system of advanced re...
AbstractA closed loop natural circulation system employs thermally induced density gradients in sing...
The study of the physical phenomenon of natural circulation is of importance for the development of ...
Nuclear reactor systems can be susceptible to thermal hydraulic instability under specific circumsta...
With reference to passive heat removal systems for advanced nuclear reactors, an experimental campai...
The Belgian nuclear research institute (SCK•CEN) is developing MYRRHA. MYRRHA is a flexible fastspec...
This research focuses on establishing a range of scaled separate and integral effects experiments fo...
The role of natural circulation in advanced water cooled reactor design has been extended with the a...
The main topic in this report is a new device being considered to improve nuclear reactor safety emp...
Melt fragmentation, quenching and long term coolability in a deep pool of water under reactor vessel...
In order to study the two-phase natural circulation and flow termination during a small break loss o...
This research focused on the study of the air-water two-phase flow in a scaled nuclear reactor rod b...
The full text of this article will not be available in ULIR until the embargo expires on the 08/02/2...
Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-s...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
DoctorPassive cooling based on natural circulation is utilized in core catcher system of advanced re...
AbstractA closed loop natural circulation system employs thermally induced density gradients in sing...
The study of the physical phenomenon of natural circulation is of importance for the development of ...
Nuclear reactor systems can be susceptible to thermal hydraulic instability under specific circumsta...
With reference to passive heat removal systems for advanced nuclear reactors, an experimental campai...
The Belgian nuclear research institute (SCK•CEN) is developing MYRRHA. MYRRHA is a flexible fastspec...
This research focuses on establishing a range of scaled separate and integral effects experiments fo...
The role of natural circulation in advanced water cooled reactor design has been extended with the a...
The main topic in this report is a new device being considered to improve nuclear reactor safety emp...
Melt fragmentation, quenching and long term coolability in a deep pool of water under reactor vessel...
In order to study the two-phase natural circulation and flow termination during a small break loss o...
This research focused on the study of the air-water two-phase flow in a scaled nuclear reactor rod b...
The full text of this article will not be available in ULIR until the embargo expires on the 08/02/2...
Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-s...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...