Analysis of neutronic parameters for typical TRIGA core configuration scenarios

Abstract

Typical TRIGA neutronic parameters calculation has been performed using SRAC 2006 with 3 dimensions modeling. Calculation of the criticality and power distribution with the SRAC2006 computer program is carried out in 2 stages. The first step is carried out by calculating the criticality of each fuel element and control rod using the PIJ module. Then, the second is the 3-dimensional core criticality calculation with the CITATION module. There are three core configuration scenarios calculated in this study. Calculated neutronic parameters are multiplication factor (K-Eff), radial and axial power peaking factor (PPF), radial and axial neutron distribution, and reactor core power density. The objective of this study is to conduct a safety analysis of the TRIGA reactor core configuration scenarios. The calculation results of the multiplication factor for reactor core configuration scenarios 1, 2, and 3 are 1.02996, 1.02761, and 1.02776. And the radial power peaking factors are 1.64, 1.68, and 1.89. Whereas, for axial Power Peaking Factor, it is still within the operating limits and conditions value range of 1.2. For the radial PPF, it can be concluded that the core configuration scenario 1 and scenario 2 can be considered as the safe core configuration because their radial PPF values are close to the operating limit and condition for this typical TRIGA reactor. The reactor core configuration scenario 3 has radial Power Peaking Factor values that exceeds operating limits and conditions for the TRIGA reactor so this scenario cannot be used to operate the reactor. The closer the radial PPF to the operating limit and condition value, the safer the reactor core configuration.