Coolant Comparison Study of HTTR (High Temperature Test Reactor) for 30 MWt using UO2, (Th,U-233)O2 and (U,Pu)O2 Fuel
Fauzan Ghilman Anshari (a*), Abdul Waris (b)
a) Bandung Institute of Technology, Department of Physics, Jl. Ganesa 10, 40132, Bandung, Indonesia
fauzan.ghilman[at]gmail.com
b) Bandung Institute of Technology, Nuclear Physics and Biophysics Research Division, Department of Physics, Jl. Ganesa 10, 40132, Bandung, Indonesia
Abstract
High Temperature Test Reactor (HTTR) is one type of IV generation reactor with high temperature gas-cooled designed with low-enriched uranium. The purpose of this study is to compare various coolants in the reactor to obtain optimal coolant. Coolant is a material used to cool the reactor. In this study compared three types of material, namely Helium, Pb-Bi and CO2. In this study also calculated with three types of reactor fuel, namely UO2, (Th,U-233)O2, and (U,Pu)O2. The parametric survey conducted is to do enrichment variations between 1 - 10%. The parametric survey results that meet the operating targets for UO2 and (Th, U-233)O2 fuels are 5% for Helium coolers, 6% for Pb-Bi coolers and 4% for CO2 coolers. Whereas fuel (U,Pu)O2 only reached the operating target for 9% enrichment on CO2 coolers. It was found that CO2 coolers were the best coolers among the three coolers compared. The reactor cell calculations are performed using the SRAC 2006 program, and utilize JENDL4.0 nuclide data.
Keywords: coolant, enrichment, HTTR, neutronic aspects
Topic: Nuclear Science and Engineering