Essays about: "thermal hydraulic system code"

Showing result 1 - 5 of 8 essays containing the words thermal hydraulic system code.

1. 1. Thermal-hydraulic safety analysis of the HTTU and GEMINI+ cores in TRACE

   University essay from KTH/Fysik

   Author : Eva Joosten; [2022]
   Keywords : HTGR; TRACE; Thermal-Hydraulics; Safety; Heat Transfer; HTGR; TRACE; Termisk-Hydraulik; Säkerhet; Värmeöverföring;

   Abstract : 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

3. 2. Pressure loss characterization for cooling and secondary air system components in gas turbines

   University essay from Luleå tekniska universitet/Institutionen för teknikvetenskap och matematik

   Author : Frida Isaksson; [2017]
   Keywords : Gas turbines; cooling and secondary air system; pressure losses; discharge coefficient; minor loss; one-dimensional modelling;

   Abstract : There is a constant struggle to increase the efficiency in gas turbines, where one method is to have a higher inlet temperature to the turbine. Often, this results in temperatures higher than the critical temperature of the materials, which makes cooling of the components an important part of the turbine. READ MORE

4. 3. CFD-analysis of buoyancy-driven flow inside a cooling pipe system attached to a reactor pressure vessel

   University essay from Linköpings universitet/Mekanisk värmeteori och strömningslära; Linköpings universitet/Tekniska högskolan

   Author : Jens Petersson; [2014]
   Keywords : CFD; OpenFOAM; LES; nuclear reactor pressure vessel;

   Abstract : In this work a cooling system connected to a reactor pressure vessel has been studied using the CFD method for the purpose of investigating the strengths and shortcomings of using CFD as a tool in similar fluid flow problems within nuclear power plants. The cooling system is used to transport water of 288K (15°C) into a nuclear reactor vessel filled with water of about 555K (282°C) during certain operating scenarios. READ MORE

5. 4. TRACE Analysis of LOCA Transients Performed on FIX-II Facility

   University essay from KTH/Kärnkraftssäkerhet

   Author : XIAO HU; [2012]
   Keywords : LOCA; TRACE; thermal-hydraulics transient; sensitivity analysis;

   Abstract : 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

6. 5. Validation of TRACE Code against ROSA/LSTF Test for SBLOCA of Pressure Vessel Upper-Head Small Break

   University essay from KTH/Kärnkraftssäkerhet

   Author : Mian Xing; [2012]
   Keywords : SBLOCA; LSTF; TRACE; thermal-hydraulics transient; safety analysis;

   Abstract : 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