Comparison of Several Thermal Conductivity Constants for Thermal Hydraulic Calculation of Pebble Bed Reactor

International Conference on Energy Sciences 2016

能源学;物理学

Irwanto, Dwi^1 ; Setiadipura, Topan^2 ; Pramutadi, Asril^1

Nuclear Physics and Biophysics Research Group, Department of Physics, Institut Teknologi Bandung, Jl. Ganesha No 10, Bandung

40132, Indonesia^1

Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency of Indonesia (BATAN), Puspiptek Complex OB. No. 80, Serpong, Tangerang Selatan

15310, Indonesia^2

关键词: Computer codes;    Fissile materials;    Porous medium;    Randomly distributed;    Reactor systems;    Safety features;    Severe nuclear accident;    Thermal-hydraulic calculations;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/877/1/012031/pdf
DOI  :  10.1088/1742-6596/877/1/012031

来源: IOP

【 摘 要 】

There are two type of High Temperature Gas Reactor (HTGR), prismatic and pebble bed. Pebble Bed type has unique configuration because the fuels are randomly distributed inside the reactor core. In term of safety features, Pebble Bed Reactor (PBR) is one of the most promising reactor type in avoiding severe nuclear accidents. In order to analyze heat transfer and safety of this reactor type, a computer code is now under development. As a first step, calculation method proposed by Stroh [1] is adopted. An approach has been made to treat randomly distributed pebble balls contains fissile material inside the reactor core as a porous medium. Helium gas act as coolant on the reactor system are carrying heat flowing in the area between the pebble balls. Several parameters and constants are taken into account in the new developed code. Progress of the development of the code especially comparison of several thermal conductivity constants for a certain PBR-case are reported in the present study.