Published July 2014 | Version v1
Journal article

Thermal-hydraulics numerical analyses of Pebble Bed Advanced High Temperature Reactor hot channel

  • 1. University of Chinese Academy of Sciences, Beijing (China)
  • 2. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus (China)
  • 3. Key Laboratory of Nuclear Radiation and Nuclear Energy Technology, Chinese Academy of Sciences, Shanghai (China)

Description

Background: The thermal hydraulics behavior of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) hot channel was studied. Purpose: We aim to analyze the thermal-hydraulics behavior of the PB-AHTR, such as pressure drop, temperature distribution of coolant and pebble bed as well as thermal removal capacity in the condition of loss of partial coolant. Methods: We used a modified FLUENT code which was coupled with a local non-equilibrium porous media model by introducing a User Defined Scalar (UDS) in the calculation domain of the reactor core and subjoining different resistance terms (Ergun and KTA) to calculate the temperature of coolant, solid phase of pebble bed and pebble center in the core. Results: Computational results showed that the resistance factor has great influence on pressure drop and velocity distribution, but less impact on the temperature of coolant, solid phase of pebble bed and pebble center. We also confirmed the heat removal capacity of the PB-AHTR in the condition of nominal and loss of partial coolant conditions. Conclusion: The numerical analyses results can provide a useful proposal to optimize the design of PB-AHTR. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Techniques
Journal Volume
37
Journal Issue
7
Journal Page Range
[8 p.]
ISSN
0253-3219

Optional Information

Notes
16 figs., 2 tabs., 17 refs. 070602-1-070602-8