Neutronic and thermal-hydraulic performance analysis of a novel thorium-based fuel in dual-cooled annular assemblies for SMR applications
A coupled neutronic and thermal-hydraulic assessment is performed for a dual-cooled annular fuel concept applied to light-water SMR conditions. A mixed thorium-based oxide, (Th-233U-235U)O2, is evaluated against conventional UO2 and solid-pin benchmarks while sweeping the inner moderator radius (0.05-0.43165 cm) at constant fuel volume. The thorium annular cases sustain an infinite multiplication factor (kinf) of 1.002-1.003 at EOC and achieve 3-batch discharge burnups of 166.3-173.5 GWd/t, compared with 142.4 GWd/t for solid UO2. Radial peaking remains low (maximum PPF ≈ 1.056, well below the 1.65 Westinghouse-types PWR design limit). All configurations exhibit negative FTC and MTC, with stronger negative feedback at larger inner radii. Thermal-hydraulic results show smooth coolant heating and robust DNBR margins (minimum ∼ 2.3) with negligible sensitivity to inner radius. These outcomes support the feasibility of thorium-based annular fuel for SMR deployment with improved fuel utilization and preserved safety margins.
Authors
- Ouadie Kabach (ORCID: https://orcid.org/0000-0002-3978-7555)
- Yasin Genç (ORCID: https://orcid.org/0000-0002-2786-4824)
- Sinem Uzun (ORCID: https://orcid.org/0000-0002-2814-1062)
- Hamid Amsil (ORCID: https://orcid.org/0000-0003-2195-3268)
- Hanan Rifai (ORCID: https://orcid.org/0009-0004-5602-7314)
- Bedrettin Uzun
- Zouhair Sadoune
- El Mahjoub Chakir
Publication Details
- Journal
- Springer Link (Chiba Institute of Technology)
- Published
- 2026-02-03
- DOI
- https://doi.org/10.1051/epjconf/202635001003/pdf
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 0.00