Essays about: "System Thermal-Hydraulics"
Showing result 1 - 5 of 7 essays containing the words System Thermal-Hydraulics.
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1. Thermal-hydraulic safety analysis of the HTTU and GEMINI+ cores in TRACE
University essay from KTH/FysikAbstract : With the coming of Generation IV systems, there is a need for thermal-hydraulic codes to model such advanced reactors. Codes for High Temperature Gas-cooled Reactors (HTGRs) already exist, but often suffer from insufficient validation and little user experience. READ MORE
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2. Simulation of IB-LOCA in TRACE : A semi-blind study of numerical simulations compared to the PKL test facility
University essay from Uppsala universitet/Tillämpad kärnfysikAbstract : This thesis studied the performance of the thermal hydraulic software TRACE applied on an intermediate sized break (IB) happening on the cold leg in a pressurized water reactor (PWR), causing a loss-of-coolant accident (LOCA). The same accident has previously been simulated in the PKL Test Facility, which is a scaled version of a PWR and is used to simulate transients stemming from different accidents. READ MORE
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3. Thermal Hydraulics Simulations for Nuclear Energy
University essay from Uppsala universitet/Tillämpad kärnfysikAbstract : .... READ MORE
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4. TRACE Analysis of LOCA Transients Performed on FIX-II Facility
University essay from KTH/KärnkraftssäkerhetAbstract : As a latest developed computational code, TRACE is expected to be useful and effective for analyzing the thermal-hydraulic behaviors in design, licensing and safety analysis of nuclear power plant. However, its validity and correctness have to be verified and qualified before its application into industry. READ MORE
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5. Validation of TRACE Code against ROSA/LSTF Test for SBLOCA of Pressure Vessel Upper-Head Small Break
University essay from KTH/KärnkraftssäkerhetAbstract : OECD/NEA ROSA/LSTF project tests are performed on the Large Scale Test Facility (LSTF). LSTF is a full-height, full-pressure and 1/48 volumetrically-scaled two-loop system which aims to simulate Japanese Tsuruga-2 Westinghouse-type 4-loop PWR. READ MORE