Kinetic parameters analysis for HTR-10 reactor at the static and transient aspect

The reactor of HTR (High Temperature Gas Cooled Reactor) is a type of nuclear reactor that using graphite as a moderator and cooled with helium gas. Indonesia has planned to build an experimental power reactor or RDE as a HTR type reactor with a nominal power 10 MW^th. The purpose of this study is to analyze safety design of the HTR reactor to support the RDE program. As a research object, the Chinese HTR-10 core data is used, because the reactor has almost same specification to the RDE. In this study, kinetic parameters of HTR-10 core at the static and transient condition were evaluated. The calculation of the kinetic parameters value as function of fuel temperature were performed by SRAC2006 computer code module of CITATION for R-Z model of 2 dimensional core. Input data defining macroscopic cross section homogenization of fuel and coolant was obtained from calculation using module of PIJ through double heterogeneity method. From the calculation results, it is known that during transient condition due to increase of the fuel temperature, values of the kinetic parameters such as prompt neutron lifetime, prompt neutron generation time, delayed neutron fraction, and delayed neutron fraction for each group of the HTR-10 core will be slightly decreased, whereas the delayed neutron decay constant for each group is almost unchanged. Therefore, the power change in the HTR-10 core will still proceed normally. (author)