NEUTRONIC AND THERMAL HYDRAULLIC ANALYSIS OF LFR-10 REACTOR WITH FLOW RATE OPTIMATION FOR EVERY CANAL

• Main Author: EKA PUTRA (NIM : 10214061), DANNY
• Format: Final Project
• Language: Indonesia
• Subjects: Fisika
• Online Access: https://digilib.itb.ac.id/gdl/view/26377
• Institution: Institut Teknologi Bandung

The fourth generation reactors are reactor type that being a main focus on research recently. This type of reactor is fission reactor with improvements in a lot of aspects, especially in safety technology. In this research, we use LFR-10 as reference. This type of reactor uses Lead-Bismuth Eutectic (LBE) as its coolant and it can produces 10 MW of thermal power. We are focusing on the thermal hydraulic analysis, especially its natural circulation. We start from neutronic analysis of this reactor to get flux distribution. We use this information to get power distribution by normalization. After that, we analyse temperature distribution for every mesh in reactor core. From that analysis, we get that outlet temperature is different for every canal. This fenomena leads to different pressure for every canal. Further analysis, we adjust mass flux to minimize the deviation of pressure by adding more pressure drop in the edge of reactor core. In practice, we can add orifice plate to do that. The result is the pressure is less deviated and the outlet temperature as well.