Essays about: "Thermal-Hydraulics"

Showing result 1 - 5 of 8 essays containing the word Thermal-Hydraulics.

  1. 1. Thermal Hydraulics Simulations for Nuclear Energy

    University essay from Uppsala universitet/Tillämpad kärnfysik

    Author : Wilhelm Thunberg; [2022]
    Keywords : Simulation; Thermal Hydraulics; Nuclear Energy; CFD; Sub-channel; System Codes; Trace; Cobra; DNS; LES; RANS;

    Abstract : .... READ MORE

  2. 2. Feasibility study on Thermal Anemometry at LWR conditions

    University essay from KTH/Fysik

    Author : Abishek Baskar; [2021]
    Keywords : Nuclear Enginnering; Thermal-Hydraulics; Instrumentation; Material technology; Fluid Dynamics. Light water reactors;

    Abstract : Dryout and Departure from Nucleate boiling (DNB) are utmost thermal-hydraulic concerns for the safety of LWRs. The behavior of two-phase flows at these conditions is still not fully understood. There is at least a need for a good local velocity and void fraction database at these conditions. READ MORE

  3. 3. Comparison of MAAP and MELCOR : and evaluation of MELCOR as a deterministic tool within RASTEP

    University essay from Uppsala universitet/Tillämpad kärnfysik

    Author : Klas Sunnevik; [2014]
    Keywords : MELCOR; MAAP; severe accident; nuclear; radioactive; radioactivity; thermal hydraulics; core cooling systems; nuclear power; bar; reactor; per; RASTEP; MELCOR; MAAP; allvarliga incidenter; kärnkraft; radioaktiv; radioaktivitet; termohydraulik; härdnödkylning; nödsystem; kylsystem; termodynamik; reaktor; bwr; pwr; RASTEP;

    Abstract : This master's thesis is an investigation and evaluation of MELCOR (a software tool for severe accident analyses regarding nuclear power plants), or more correctly of the (ASEA-Atom BWR 75) reactor model developed for version 1.8.6 of MELCOR. READ MORE

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

    University essay from KTH/Kärnkraftsäkerhet

    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

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

    University essay from KTH/Kärnkraftsäkerhet

    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