Nurhidayah, Nurhidayah and Monado, Fiber and Ariani, Menik and Kaban, Hadir (2024) Neutronic Analysis of the Candle Gas-Cooled Fast Reactor (GFR) Core with Metallic Uranium (U-10%wtZr) Fuel Based on 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
This study conducts a neutron analysis of the CANDLE Gas-Cooled Fast Reactor (GFR) core with Uranium Metallic (U-10%wtZr) fuel using the OpenMC software. The analysis aims to understand the reactor core's neutron flux distribution and fission reaction rates. Results reveal higher neutron fluxes in t
| Item Type: | Conference or Workshop Item (UNSPECIFIED) |
|---|---|
| Date Deposited: | 04 Mar 2026 17:54 |
| Last Modified: | 16 Apr 2026 23:02 |
| URI: | http://eprints.eai.eu/id/eprint/50341 |
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