Kurniawan, M Aldi and Ariani, Menik and Monado, Fiber and Johan, Akmal (2024) Neutronic Calculation of Mixed Oxide Fuel for Gas-Cooled Fast Reactor using Monte Carlo code OpenMC. In: Proceedings of the 3rd Sriwijaya International Conference on Basic and Applied Sciences, SICBAS 2023, November 3, 2023, Palembang, Indonesia.
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Abstract
A fundamental aspect of nuclear power is using the prepared nuclear fuel once and then dumping it as waste, most of it can be recycled, thus closing the fuel cycle. The current means of doing this is by separating and recycling the plutonium. This plutonium is then blended with natural uranium to fo
| Item Type: | Conference or Workshop Item (UNSPECIFIED) |
|---|---|
| Date Deposited: | 04 Mar 2026 17:56 |
| Last Modified: | 16 Apr 2026 23:01 |
| URI: | http://eprints.eai.eu/id/eprint/50486 |
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