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Effect of addition Np, Am, and Cm as minor actinides on (U-10%Zr) fuel cell design
This study aims to design a fuel cell based on Natural Uranium Metal (U-10%wtZr) with the addition of minor actinides, such as Am-241, Np-237, and Cm-244. The coolant used was Helium, and the cladding was carried out with Stainless Steel (SS316). This fuel cell is pin-shaped with a diameter of 1.4 c...
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creator | Ristika, Ade Monado, Fiber Royani, Idha Arsali Ariani, Menik Su’ud, Zaki |
description | This study aims to design a fuel cell based on Natural Uranium Metal (U-10%wtZr) with the addition of minor actinides, such as Am-241, Np-237, and Cm-244. The coolant used was Helium, and the cladding was carried out with Stainless Steel (SS316). This fuel cell is pin-shaped with a diameter of 1.4 cm and was then tested using 5% enrichment with and without minor actinide. Calculation was then carried out based on the neutron transport equation using SRAC. The results showed that the value of the infinite multiplication factor (KInf) after the addition of 5% Am-241 and Np-237 with 5% enrichment has not reached a critical state and it decreased at the beginning of the burn-up time. However, as more percent of Cm-244 was added, the KInf increased and reached a critical state at a concentration of 4% with a value of 1.001198. |
doi_str_mv | 10.1063/5.0208865 |
format | conference_proceeding |
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The coolant used was Helium, and the cladding was carried out with Stainless Steel (SS316). This fuel cell is pin-shaped with a diameter of 1.4 cm and was then tested using 5% enrichment with and without minor actinide. Calculation was then carried out based on the neutron transport equation using SRAC. The results showed that the value of the infinite multiplication factor (KInf) after the addition of 5% Am-241 and Np-237 with 5% enrichment has not reached a critical state and it decreased at the beginning of the burn-up time. However, as more percent of Cm-244 was added, the KInf increased and reached a critical state at a concentration of 4% with a value of 1.001198.</abstract><cop>Melville</cop><pub>American Institute of Physics</pub><doi>10.1063/5.0208865</doi><tpages>10</tpages></addata></record> |
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identifier | ISSN: 0094-243X |
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source | American Institute of Physics:Jisc Collections:Transitional Journals Agreement 2021-23 (Reading list) |
subjects | Actinides Americium 241 Austenitic stainless steels Curium 244 Fuel cells Multiplication Neptunium isotopes Transport equations Uranium Zirconium |
title | Effect of addition Np, Am, and Cm as minor actinides on (U-10%Zr) fuel cell design |
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