Analysis on Transmutation of Long-Lived Fission Products from PWR Spent Fuel Using the 30-MW(thermal) RSG-GAS Reactor. (1st December 2020)

• Record Type: Journal Article
• Authors: Setiawan, M. Budi; Udiyani, P. Made; Kuntjoro, S.; Husnayani, I.; Surbakti, T.
• Is Part Of: Nuclear technology. Volume 206:Number 12(2020)
• Page Start: 1945
• Page End: 1950
• Publication Date: 2020-12-01
• Subjects: Transmutation -- long-lived fission products -- RSG-GAS research reactor; Nuclear engineering -- Periodicals; Nuclear engineering; Nuclear Physics; Periodicals; Periodicals; 621.48
• DOI: 10.1080/00295450.2020.1720558
• Languages: English
• ISSNs: 1943-7471

Abstract

Abstract: The use of the RSG-GAS research reactor as a transmutation reactor is analyzed to study its effectiveness for transmuting long-lived fission products (LLFPs), particularly 129 I and 99 Tc. Both radionuclides selected are assumed as discharged from of a 1000-MW(electric) pressurized water reactor (PWR) spent fuel. If these radionuclides are stored in sustainable geologic disposal, they will require high-cost handling due to their special shielding. In one cycle of PWR1000 operation, the 99 Tc produced is 43.7 kg and 129 I is 9.5 kg in its spent fuel. Considering reactor safety, the maximum target mass permitted to be transmuted in the RSG-GAS is 3.0 kg for the 99 Tc and 5.0 kg for the 129 I. In 1 year of (five cycles) operation, the 99 Tc and 129 I targets would be reduced by 126 and 290 g, respectively. Although it has the potentiality to safely transmute LLFP targets in its core, RSG-GAS requires longer irradiation time (about 20 years) to entirely transmute the targets.