Szczegóły publikacji
Opis bibliograficzny
High-fidelity Monte Carlo modelling of the HTGR fuel cycle for fuel utilization optimization and nuclear safety assurance / Jerzy CETNAR // Energies [Dokument elektroniczny]. — Czasopismo elektroniczne ; ISSN 1996-1073 . — 2025 — vol. 18 iss. 24 art. no. 6410, s. 1–24. — Wymagania systemowe: Adobe Reader. — Bibliogr. s. 23–24, Abstr. — Publikacja dostępna online od: 2025-12-08
Autor
Słowa kluczowe
Dane bibliometryczne
| ID BaDAP | 165215 |
|---|---|
| Data dodania do BaDAP | 2026-01-09 |
| Tekst źródłowy | URL |
| DOI | 10.3390/en18246410 |
| Rok publikacji | 2025 |
| Typ publikacji | artykuł w czasopiśmie |
| Otwarty dostęp |  |
| Creative Commons | |
| Czasopismo/seria | Energies |
Abstract
This paper presents a numerical study of fuel cycle performance and time–space characteristics of a research-scale high temperature gas-cooled reactor (HTGR) using high-fidelity Monte Carlo simulations with continuous-energy and double-heterogeneity modeling. Three core geometries (V1, V2, V3) and three fuel enrichment levels (5%, 8%, 12%) were analyzed with axial batch refueling strategies. Results show a strong dependence of fuel utilization on geometry and enrichment. The V2 configuration achieves the best performance, with sub-cycle lengths up to 550 days and fuel utilization over 91% at 12% enrichment. V1 and V3 yield shorter cycles but maintain stable power and temperature profiles. In all cases, fuel temperature remained below 1200 K, ensuring a wide safety margin. The similarity of power distributions for different enrichments indicates that a single core design can accommodate various fuel types without compromising safety. These findings support the selection of V2 as a reference configuration for a future HTGR research reactor.
