Sökning: "Thermal-hydraulic correlations"
Hittade 5 avhandlingar innehållade orden Thermal-hydraulic correlations.
1. Assessment and improvements of thermal-hydraulic correlations and methods for the analysis of the Jules Horowitz Reactor
Sammanfattning : Nuclear research reactors are used to test materials for current and future nuclear technologies, and to produce radioisotopes for medical purposes. Most of the existing Material Testing Reactors in Europe have operated for more than 50 years and new ones are needed. LÄS MER
2. Improvement of the nuclear safety code CATHARE based on thermal-hydraulic experiments for the Jules Horowitz Reactor
Sammanfattning : The Jules Horowitz Reactor (JHR) is a material testing research reactor under construction at CEA-Cadarache (France). One of the computer codes employed in the safety analysis of this reactor is the thermal-hydraulic system code CATHARE. LÄS MER
3. Steam condensation in a water pool and its effect on thermal stratification and mixing
Sammanfattning : The Pressure Suppression Pool (PSP) of a Boiling Water Reactor (BWR) is a large heat sink designed to limit the containment pressure by condensing steam released from the primary coolant system. The development of thermal stratification is a safety concern since it leads to higher containment pressures than in completely mixed conditions, and can affect the performance of systems such as the emergency core cooling and containment spray, which the use PSP as a source of water. LÄS MER
4. Performance Analysis and Optimal Design of Heat Exchangers and Heat Exchanger Networks
Sammanfattning : This thesis presents a study on performance analysis and optimal design of heat exchangers and heat exchanger networks. The study includes an experimental investigation of steam condensation in plate heat exchangers, optimal design of plate heat exchangers and plate-fin heat exchangers, and optimization of heat exchanger networks. LÄS MER
5. Analysis methodology for RBMK-1500 core safety and investigations on corium coolabiblty during a LWR sever accidnet
Sammanfattning : This thesis presents the work involving two broad aspectswithin the field of nuclear reactor analysis and safety. Theseare: - development of a fully independent reactor dynamics andsafety analysis methodology of the RBMK-1500 core transientaccidents and - experiments on the enhancement of coolabilityof a particulate bed or a melt pool due to heat removal throughthe control rod guide tubes. LÄS MER