STUDY NEUTRONIC OF SMALL PB-BI COOLED NON-REFUELLING NUCLEAR POWER PLANT REACTOR (SPINNOR) WITH HEXAGONAL GEOMETRY CALCULATION

• Main Author: NUR KRISNA (NIM : 10211040), DWITA
• Format: Final Project
• Language: Indonesia
• Online Access: https://digilib.itb.ac.id/gdl/view/20047
• Institution: Institut Teknologi Bandung

Nuclear reactor technology developed rapidly over time, particularly in the development of the Nuclear Power Plant (NPP). The utilization of nuclear energy in power generation systems has been progressing phase of the first generation to the fourth generation. This final project discusses the analysis neutronic onecooled <br /> <br /> <br /> fast reactor type Pb-Bi is capable of operating up to 20 years without refuelling called SPINNOR. This reactor used Thorium Uranium Nitride as fuel and operate at a power range 100-500MWt NPPs. The method of calculation used a computer simulation program utilizing SRAC. SRAC program used for the calculation of homogenization modified with CITATION calculation. SPINNOR reactor was designed with hexagonal geometry shaped terrace that radially divided into three regions, the outer region with the highest percentage of fuel, the middle region with medium percentage, and the inner region with the lowest percentage. SPINNOR fast reactor was operated for 20 years with percentage variance of fuel by 7%, 7.75% and 8.5%. The neutronic parameters analyzed in this study include level burn-up, power density, effective multiplication factor (keff), reactivity, and conversion ratio. Neutronic calculation and analysis show that the design can be optimized in a fast reactor for thermal power output SPINNOR 300MWt with a fuel fraction 60% and variations in fuel enrichment 7% - 8.5%