PRELIMINARY STUDY ON TH-ENRICHED U UTILIZATION IN MOLTEN SALT REACTOR (MSR) MINIFUJI

• Main Author: Lathiiful Quluub, Ahmad
• Format: Final Project
• Language: Indonesia
• Subjects: Fisika
• Online Access: https://digilib.itb.ac.id/gdl/view/35323
• Institution: Institut Teknologi Bandung

Molten Salt Reactor (MSR) is gen IV reactor with liquid form fuel, melted in the homogenous molten salt coolant, so it hasn’t burnup distribution. MSR improve reactor security, non-proliferation issue, and be able to online refueling. The advantages can solve the world energy crisis. The research is the preliminary study on Th-enriched U in miniFUJI. In this reactor, the variations are based on reactor thermal power by 25, 30, 35, and 40 MWt. Then the enrichment variations are applied with 20% maximum enrichment. It is due to the maximum enrichment regulation in commercial reactors. Then fuel/graphite ratio is varied by 25:75, 20:80, 15:85, and 10:90. The initial composition of 71.76% LiF, 16% BeF2, 12% ThF4 and 0.24% UF4, have not reached the critical level in 20 years. Then the addition of UF4 is varied by 0 - 12%. The calculation use SRAC2006 and JENDL 4.0. The result, MSR miniFUJI 25 MWt can reach the critical level with 16% U enrichment, miniFUJI 30 MWt 17,5%, miniFUJI 35 MWt 19%, and miniFUJI 40 MWt 20%. Increasing reactor thermal power causes more enrichment is needed. High enrichment reduces UF4 composition. Additions of fuel/graphite ratio effects reducing the enrichment are needed.