Sökning: "Reactor system code"

Visar resultat 1 - 5 av 20 avhandlingar innehållade orden Reactor system code.

1. 1. Development of an Improved Thermal-Hydraulic Modeling of the Jules Horowitz Reactor

   Författare :Reijo Pegonen; Henryk Anglart; Yann Bartosiewicz; KTH; []
   Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Jules Horowitz Reactor; CATHARE2; STAR-CCM ; FLICA4; Material Testing Reactor; Computational Fluid Dynamics; System code; Reactor modeling;

   Sammanfattning : The newest European high performance material testing reactor, the Jules Horowitz Reactor, is under construction at CEA Cadarache research center in France. The reactor will support existing and future nuclear reactor technologies, with the first criticality expected at the end of this decade. LÄS MER

3. 2. Input Calibration, Code Validation and Surrogate Model Development for Analysis of Two-phase Circulation Instability and Core Relocation Phenomena

   Författare :Viet-Anh Phung; Pavel Kudinov; Cristophe Demaziere; KTH; []
   Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; Reactor system code; input calibration; code validation; surrogate model; two-phase circulation flow instability; in-vessel core relocation; genetic algorithm; artificial neural network; Reaktorsystemkod; indata kalibrering; kodvalidering; surrogatmodell; två-fas cirkulationsflöde; instabilitet; härdrelokering i reaktortanken; genetisk algoritm; artificiella neurala nätverk; Fysik; Physics;

   Sammanfattning : Code validation and uncertainty quantification are important tasks in nuclear reactor safety analysis. Code users have to deal with large number of uncertain parameters, complex multi-physics, multi-dimensional and multi-scale phenomena. LÄS MER

4. 3. Effective Spatial Mapping for Coupled Code Analysis of Thermal–Hydraulics/Neutron–Kinetics of Boiling Water Reactors

   Författare :Joanna Peltonen; Weimin Ma; Maria Avramova; KTH; []
   Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; Boiling Water Reactor; RELAP5; TRACE; PARCS; Coupled TH NK analysis; Spatial Mapping; Turbine Trip; Feedwater Transient; Control Rod Drop; Reactor Stability; Hierarchical Clustering; kokvattenreaktor; reaktoranalys; RELAP5; TRACE; PARCS; TH NK analys; turbin tripp; matarvatten transient; fallande styrstav; reaktor stabilitet; hierarkisk klustringsmetodik; SRA - Energy; SRA - Energi;

   Sammanfattning : Analyses of nuclear reactor safety have increasingly required coupling of full three dimensional neutron kinetics (NK) core models with system transient thermal–hydraulics (TH) codes.  In order to produce results within a reasonable computing time, the coupled codes use two different spatial description of the reactor core. LÄS MER

5. 4. Assessment and improvements of thermal-hydraulic correlations and methods for the analysis of the Jules Horowitz Reactor

   Författare :Alberto Ghione; Chalmers tekniska högskola; []
   Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; NATURVETENSKAP; NATURAL SCIENCES; Flow instability; Uncertainty; Narrow channels; Jules Horowitz Reactor; Safety analysis; Critical heat flux; Thermal-hydraulic correlations; Heat transfer; Best-Estimate; Material Testing 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

7. 5. Improvement of the nuclear safety code CATHARE based on thermal-hydraulic experiments for the Jules Horowitz Reactor

   Författare :Alberto Ghione; Chalmers tekniska högskola; []
   Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; nuclear research reactor; fully developed boiling; single-phase heat transfer; CATHARE; laminar-turbulent transition; narrow rectangular channels; JHR; single-phase friction; SULTAN-JHR;

   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