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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Bibliographic Details
Main Authors: Ristika, Ade, Monado, Fiber, Royani, Idha, Arsali, Ariani, Menik, Su’ud, Zaki
Format: Conference Proceeding
Language:English
Subjects:
Actinides
Americium 241
Austenitic stainless steels
Curium 244
Fuel cells
Multiplication
Neptunium isotopes
Transport equations
Uranium
Zirconium
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Summary: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.
ISSN:0094-243X
1551-7616
DOI:10.1063/5.0208865