Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code
Yazarlar (3)
Prof. Dr. Turgay KORKUT Sinop Üniversitesi, Türkiye
Prof. Dr. Ayhan Kara Giresun Üniversitesi, Türkiye
Hatun Korkut Sinop Üniversitesi, Türkiye
| Makale Türü | Özgün Makale (SSCI, AHCI, SCI, SCI-Exp dergilerinde yayınlanan tam makale) | ||
| Dergi Adı | KERNTECHNIK (Q4) | ||
| Dergi ISSN | 0932-3902 Dergi Bilgileri (2016) | ||
| Dergi Tarandığı Indeksler | SCI | ||
| Makale Dili | İngilizce | Basım Tarihi | 12-2016 |
| Cilt / Sayı / Sayfa | 81 / 6 / 599–608 | DOI | 10.3139/124.110580 |
| Makale Linki | http://www.hanser-elibrary.com/doi/10.3139/124.110580 | ||
| UAK Araştırma Alanları |
Nükleer Fizik
|
||
| Özet |
| Ultra High Temperature Ceramics (UHTCs) have low density and high melting point. So they are useful materials in the nuclear industry especially reactor core design. Three UHTCs (silicon carbide, vanadium carbide, and zirconium carbide) were evaluated as the nuclear fuel cladding materials. The SERPENT Monte Carlo code was used to model CANDU, PWR, and VVER type reactor core and to calculate burnup parameters. Some changes were observed at the same burnup and neutronic parameters (keff, neutron flux, absorption rate, and fission rate, depletion of U-238, U-238, Xe-135, Sm-149) with the use of these UHTCs. Results were compared to conventional cladding material zircalloy. |
| Anahtar Kelimeler |
BM Sürdürülebilir Kalkınma Amaçları
| Atıf Sayıları | |
| Web of Science | 5 |
| Google Scholar | 5 |