The calculation of neutron flux using Monte Carlo method
| dc.authorwosid | DÜZ, Mehtap/AAS-3672-2020 | |
| dc.contributor.author | Gunay, Mehtap | |
| dc.contributor.author | Bardakci, Hilal | |
| dc.date.accessioned | 2024-08-04T21:01:19Z | |
| dc.date.available | 2024-08-04T21:01:19Z | |
| dc.date.issued | 2017 | |
| dc.department | İnönü Üniversitesi | en_US |
| dc.description | 3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT) -- MAY 10-12, 2017 -- Adana, TURKEY | en_US |
| dc.description.abstract | In this study, a hybrid reactor system was designed by using 99-95% Li20Sn80 + 1-5% RG-Pu, 99-95% Li20Sn80 + 1-5% RG-PuF4, and 99-95% Li20Sn80 + 1-5% RG-PuO2 fluids, ENDF/B-VII. 0 evaluated nuclear data library and 9Cr2WVTa structural material. The fluids were used in the liquid first wall, liquid second wall (blanket) and shield zones of a fusion-fission hybrid reactor system. The neutron flux was calculated according to the mixture components, radial, energy spectrum in the designed hybrid reactor system for the selected fluids, library and structural material. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code. | en_US |
| dc.description.sponsorship | Inonu University [2015/68] | en_US |
| dc.description.sponsorship | This work was supported by Inonu University Research fund with the project number 2015/68. | en_US |
| dc.identifier.doi | 10.1051/epjconf/201715401025 | |
| dc.identifier.issn | 2100-014X | |
| dc.identifier.uri | https://doi.org/10.1051/epjconf/201715401025 | |
| dc.identifier.uri | https://hdl.handle.net/11616/104292 | |
| dc.identifier.volume | 154 | en_US |
| dc.identifier.wos | WOS:000426429000025 | en_US |
| dc.identifier.wosquality | N/A | en_US |
| dc.indekslendigikaynak | Web of Science | en_US |
| dc.language.iso | en | en_US |
| dc.publisher | E D P Sciences | en_US |
| dc.relation.ispartof | 3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (Tesnat 2017) | en_US |
| dc.relation.publicationcategory | Konferans Öğesi - Uluslararası - Kurum Öğretim Elemanı | en_US |
| dc.rights | info:eu-repo/semantics/openAccess | en_US |
| dc.subject | Breeder Apex Reactor | en_US |
| dc.subject | Radiation-Damage | en_US |
| dc.subject | Fusion Breeder | en_US |
| dc.subject | Structural Material | en_US |
| dc.title | The calculation of neutron flux using Monte Carlo method | en_US |
| dc.type | Conference Object | en_US |
