Design studies for A 50 MWth molten salt fast reactor
Yazarlar (4)
Sümer Şahin
Istanbul Nisantasi University, Türkiye
Istanbul Nisantasi University, Türkiye
Prof. Dr. Hacı Mehmet Şahin Gazi Üniversitesi, Türkiye
Doç. Dr. Güven Tunç Gazi Üniversitesi, Türkiye
Dr. Öğr. Üyesi Hüseyin ŞAHİNER Sinop Üniversitesi, Türkiye
| Makale Türü | Özgün Makale (SSCI, AHCI, SCI, SCI-Exp dergilerinde yayınlanan tam makale) | ||
| Dergi Adı | Progress in Nuclear Energy (Q1) | ||
| Dergi ISSN | 0149-1970 Dergi Bilgileri (2023) | ||
| Dergi Tarandığı Indeksler | SCI-Expanded | ||
| Makale Dili | İngilizce | Basım Tarihi | 12-2023 |
| Cilt / Sayı / Sayfa | 166 / 1 / – | DOI | 10.1016/j.pnucene.2023.104964 |
| Makale Linki | http://dx.doi.org/10.1016/j.pnucene.2023.104964 | ||
| UAK Araştırma Alanları |
Nükleer Bilimler
Nükleer Uygulamalar
Reaktör Teknolojisi
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| Özet |
| In this paper, design studies for a 50 MWth Molten Salt Reactor (MSR) have been carried out for the eutectic point of the molten salt mixture. Neutronic calculations are performed with the 19.75% enriched uranium and 100% 7Li isotope contained. The MCNP6 nuclear code was used with the ENDF/B-VIII nuclear data library to determine geometry dimensions and criticality. The time-evolution of Pu and other heavy isotopes in the reactor are calculated with the interface code MCNPAS. Four models are investigated with different reactor vessel materials: Model 1: Ni alloy (NiCrW-Hastelloy steel), Model 2: Beryllium, Model 3: Graphite and Model 4: Silicon Carbide (SiC). For the respective models, time-dependent criticality calculations are performed with a startup criticality value of keff = 1.0262, 1.0298, 1.0404, and 1.0223. The 235U consumed for the corresponding models over the 10 years of reactor operation are … |
| Anahtar Kelimeler |
| Fast reactor | Liquid fuel | Molten salt-fuel mixture | MSR | SMR |
Science Direct
Design studies for A 50 MWth molten salt fast reactor
BM Sürdürülebilir Kalkınma Amaçları
| Atıf Sayıları | |
| Scopus | 9 |
| Google Scholar | 14 |