Loading...

Development of a Computer Code for Thermal Hydraulic Design of a High Temperature Gas Cooled Reactor Core

Khosravi Mirzaee, Morteza | 2011

1140 Viewed
  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 42313 (46)
  4. Department: Energy Engineering
  5. Advisor(s): Ghofrani, Mohammad Bagher; Jafari, Jalil
  6. Abstract:
  7. High temperature gas cooled reactors (HTGR) are one of the most promising reactors in the new generation of world commercial reactors. They are divided into two main categories: Prismatic gas cooled reactors and pebble bed gas cooled reactors. These reactors have many advantages, such as inherent safety, high thermodynamic efficiency and the possibility of producing hydrogen. One of the most important challenges in developing these reactors is providing appropriate codes in design and simulating their performance. Two codes have been developed in this thesis. The first, THFAM, is a steady state thermal hydraulic code which helps in analyzing a fuel assembly. The second, named THCM is developed for analyzing a prismatic HTGR core. Explicit finite difference method is used in obtaining numerical solutions for the governing equations and various boundary conditions are supported by these codes. In these codes conservation of mass and axial momentum equations are used in order to obtain pressure distribution and mass flow rate in different channels. Also, conservation of energy equations are solved to obtain temperature distributions in different parts of the fuel assembly or the core. The codes have been benchmarked against the well-known Helium engineering demonstration loop (HENDEL) benchmarks and also various experimental data and analytical results from high temperature gas cooled reactors (HTTR). It has been demonstrated that the maximum relative error in thermal hydraulic hot channel analyze is about 3 percent
  8. Keywords:
  9. Finite Difference Method ; High Themprature Gas-Cooled Reactor (HTGR) ; Thermal Hydraulic Analysis Code (THAC) ; High Temperature Gas Cooled Reactors (HTTR)

 Digital Object List

  • محتواي پايان نامه
  •   view

 Bookmark

No TOC