Abstract
Thorium as fissile material has overweigh advantages compared to Uranium in order to have a long-life PWR reactor without replacement fuel. Additional of Protactinium as a burnable poison is effective to reduce excess reactivity in the beginning of the reactor operation. This study aims to analyze the neutronic, burnup fuel, thermal-hydraulic and kinetic calculations in regard to reactor safety. The calculation is performed with SRAC program using JENDL-32 as data library. The results show that the value of keff for 33 years are still in the range 1.0154 <keff<1.0171 and the burn-up level has increased, due to the additional fissile material as conversion results of Th232 and Pa231. Axial linear power distribution indicates normal distribution pattern. The coolant temperature distribution in the axial direction is quite flat. Key words: PWR, Th-232, U-233, Pa-231, neutronic, thermal-hydraulic, burn-up level, reactor kinetics
Highlights
How to Cite: Jubaidah, (2016), Preliminary Study on Small Long-Life Pressurized Water Reactor (PWR) Reactor Design Fueled Thorium with Protactinium as Burnable Poison, Jurnal Einsten Prodi Fisika FMIPA Unimed, 4 (3) : 39-45
Has many advantages compared to Uranium (U-238)
Absorption cross-section of Th- consists of neutronic, fuel burn-up, 232 (7,6b) is three times higher than U- thermal-hydraulic calculation as well as
Summary
How to Cite: Jubaidah, (2016), Preliminary Study on Small Long-Life PWR Reactor Design Fueled Thorium with Protactinium as Burnable Poison, Jurnal Einsten Prodi Fisika FMIPA Unimed, 4 (3) : 39-45. Preliminary Study on Small Long-Life PWR Reactor Design Fueled Thorium with Protactinium as Burnable Poison. Thorium (Th-232) is fertile JENDL-32 as data library and Prenpacelement for thermal nuclear reactors that v1.0.[4]. Has many advantages compared to Uranium (U-238). Natural Thorium is METHODS AND MATERIALS three times more abundant than natural The methodology in this research. Absorption cross-section of Th- consists of neutronic, fuel burn-up, 232 (7,6b) is three times higher than U- thermal-hydraulic calculation as well as
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