Neutronic analysis for fresh instrumented fuel element ID 9884 type 204 with 8.5 wt% position in existing Bandung TRIGA 2000 core

• Main Authors: Irsyad, Basuki, Prasetyo, Nailatussaadah, Mediawan, Anton
• Format: Conference Proceeding
• Language: English
• Subjects: Control rods; Fuels; Nuclear fuel elements; Nuclear fuels; Nuclear safety; Parameters; Reactivity; Reactor cores; Shutdowns
• ISSN: 0094-243X; 1551-7616
• DOI: 10.1063/5.0066703

Bandung TRIGA 2000 is a research reactor that can be operated up to 2 MWTh. Reactor core always needs reshuffling and refueling to gain safety parameters and operable conditions. Based on recent reshuffling program for Bandung TRIGA 2000 reactor core have decided to place fresh instrumented fuel element with 204 type with 8,5% wt. From last existing reshuffling program, the hot channel predicted will be at one of Ring-B position. Since the Ring-B has 6 positions and only one position will be placed with IFE; so that neutronic analysis will be required to analyze based on determined safety parameters in operating condition limit. We have conducted analysis regarding to parameters; core excess, shutdown reactivity, one stuck rods criteria, analysis of power peaking factor (PPF) axial and radial by control rods withdrawal position functions. Based on these analyses we found that the best position for this fresh instrumented Fuel element will be at B-2 position. In this position this fuel will get 16.02 kWTh with 1 MWTh operation power. Furthermore, the criticality profiles are; Fully up keff=1.01086 with core excess reactivity 1.49 $; shutdown reactivity -15.96$. Then, the fully up radial PFF is 1.672 and PPF axial 1.25. All of these results are not exceeding the operating conditions limits.