Doppler effect evaluation of the TRU-based Moroccan TRIGA Mark II reactor: applying novel methodologies
| dc.contributor.author | Mira, Mohamed |
| dc.contributor.author | el Hajjaji, O. |
| dc.contributor.author | Freixa Terradas, Jordi |
| dc.contributor.author | el Bardouni, Tarek |
| dc.contributor.author | Boukhal, Hamid |
| dc.contributor.author | Boulaich, Y. |
| dc.contributor.author | el Ghalbzouri, Tarik |
| dc.contributor.group | Universitat Politècnica de Catalunya. ANT - Advanced Nuclear Technologies Research Group |
| dc.contributor.other | Universitat Politècnica de Catalunya. Departament de Física |
| dc.date.accessioned | 2025-04-25T07:21:16Z |
| dc.date.issued | 2025-07-01 |
| dc.date.lift | 2027-07-31 |
| dc.description.abstract | The Doppler effect, commonly referred to as fuel temperature coefficient (aT), is a critical parameter that quantifies the reactivity feedback resulting from changes in fuel temperature. Understanding and accurately quantifying aT is essential for evaluating and adopting innovative fuel compositions. In this study, we present a comprehensive evaluation of aT for transuranic (TRU)-based Moroccan TRIGA Mark II reactor, employing advanced simulation techniques and methodologies based on the OpenMC code. Two novel methods are introduced and validated. The first method analyzes the contributions of the fast fission factor (e ), resonance escape probability factor (p ), thermal utilization factor (f ), and reproduction factor (¿ ) to aT . The second evaluates the Upscattering and isotope-wise contributions to gain deeper insights into the behavior of these factors. Additionally, aT is evaluated as a function of fuel burnup. For comparative purposes, the standard U-ZrH1.65 fuel is also analyzed to benchmark the behavior of the TRU-based fuel against conventional fuel types. The results reveal that TRU-based fuel, despite its high fissile content, it maintains a negative aT across the operational temperature range and throughout the reactor’s lifetime. This negative reactivity feedback is attributed to the significant thermal capture resonances of TRU-based isotopes, such 240Pu, and 242Pu, and the unique properties of the zirconium hydride matrix ZrH1.65. Although the magnitude of aT for TRU-based fuel is less negative compared to the standard U-ZrH1.65 fuel, it remains sufficiently negative to guarantee safe reactor operation. These findings are promising and suggest that further exploration of TRU-based fuels could support the development of reliable, clean, and sustainable nuclear energy systems. |
| dc.description.peerreviewed | Peer Reviewed |
| dc.description.version | Preprint |
| dc.identifier.citation | Mira, M. [et al.]. Doppler effect evaluation of the TRU-based Moroccan TRIGA Mark II reactor: applying novel methodologies. "Annals of nuclear energy", 1 Juliol 2025, vol. 217, núm. article 111353. |
| dc.identifier.doi | 10.1016/j.anucene.2025.111353 |
| dc.identifier.issn | 0306-4549 |
| dc.identifier.uri | https://hdl.handle.net/2117/428445 |
| dc.language.iso | eng |
| dc.relation.publisherversion | https://www.sciencedirect.com/science/article/abs/pii/S0306454925001707?via%3Dihub |
| dc.rights.access | Restricted access - publisher's policy |
| dc.rights.licensename | Attribution-NonCommercial-NoDerivatives 4.0 International |
| dc.rights.uri | http://creativecommons.org/licenses/by-nc-nd/4.0/ |
| dc.subject | Àrees temàtiques de la UPC::Energies::Energia nuclear |
| dc.subject.other | Doppler broadening |
| dc.subject.other | Windowed multipole method |
| dc.subject.other | Transuranic nuclides |
| dc.subject.other | TRIGA Mark II |
| dc.subject.other | OpenMC |
| dc.subject.other | Four-factor formula |
| dc.title | Doppler effect evaluation of the TRU-based Moroccan TRIGA Mark II reactor: applying novel methodologies |
| dc.type | Article |
| dspace.entity.type | Publication |
| local.citation.author | Mira, M.; el Hajjaji, O.; Freixa, J.; el Bardouni, T.; Boukhal, H.; Boulaich, Y.; el Ghalbzouri, T. |
| local.citation.number | article 111353 |
| local.citation.publicationName | Annals of nuclear energy |
| local.citation.volume | 217 |
| local.identifier.drac | 40949761 |
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