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Saeed Zare Ganjaroodi
Saeed Zare Ganjaroodi
Energy and Physics Department, Amirkabir University of Technology, 424 Hafez Ave., Tehran, Iran
Verified email at aut.ac.ir
Title
Cited by
Cited by
Year
Thermal-hydraulic modeling of CAREM-25 advanced small modular reactor using the porous media approach and COBRA-EN modified code
SZ Ganjaroodi, M Fani, E Zarifi, S Bentridi
Nuclear Engineering and Technology 56 (5), 1574-1583, 2024
52024
Stereotactic iodine-125 brachytherapy for low-grade glioma treatment: A monte carlo study
S Valizadeh, E Saeedzadeh, A Zali, H Nedaei, SZ Ganjaroodi
International Clinical Neuroscience Journal 9, e9, 2022
52022
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling
SZ Ganjaroodi, E Zarifi
Atomic Energy 134 (3), 264-274, 2023
32023
Neutronic analysis of the new proposed configuration of CAREM-25 advanced small modular reactor with enriched thorium fuel
SZ Ganjaroodi, SE Bentridi, E Zarifi, N Amrani
Engineering Research Express 7 (1), 015428, 2025
22025
Neutronic analysis of new generation TVS-2M fuel assemblies in VVER-1000 reactor type
SZ Ganjaroodi, E Zarifi, H Khameh
Radiation Physics and Chemistry 225, 112143, 2024
22024
Neutronic and safety analysis of CAREM-25 small modular reactor using supermc advanced code
S Zare Ganjaroodi, H Khameh, M Kazem Farahzadi, Y Kasesaz, E Zarifi
International Journal of Reliability, Risk and Safety: Theory and …, 2023
22023
Post closure safety assessment for near surface disposal
S Hassanlou, A Taherian, AM Farsani, SZ Ganjaroodi
Nuclear Engineering and Technology 57 (4), 103291, 2025
12025
Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software
S Mojab, E Zarifi, SZ Ganjaroodi, G Jahanfarnia
Atomic Energy 134 (5), 391-396, 2023
12023
Thermo-Hydraulic Analysis of Passive Heat Removal System (PHRS) in VVER-1000 Nuclear Reactor Using RELAP5 Code
S Zare Ganjaroodi
Nuclear Technology and Energy 1 (4), 32-42, 2023
12023
Thermal-hydraulic analysis of new generation TVS-2M fuel in VVER-1000 reactor using porous media approach method
SZ Ganjaroodi, M Fani, E Zarifi
Advances in Energy Sciences and Technologies 1 (1), 107-118, 2025
2025
T5-P6: Operational safety assessment for disposal zone in near-surface repository site
SZ Ganjaroodi, M Fani, AM Farsani, N Amrani
ICRAA’4, 193, 2025
2025
Determination of Baseline Value of Radionuclides in Iranian Near-Surface Disposal Facility
M Boroumandi, GS Zare, S Hassanlou, A Taherian, F Changizi, ...
Iranian Journal of Chemistry and Chemical Engineering 44 (5), 1338-1350, 2025
2025
Measurement of Cesium and Uranium Distribution Coefficient (Kd) in the Iranian Radioactive Repository Site
S Hassanlou, S Zare Ganjaroodi, A Maleki Farsani
Iran. J. Chem. Chem. Eng.(IJCCE) Vol 44 (03), 2025
2025
Measurement of Cesium and Uranium distribution coefficient (Kd) in the Iranian radioactive repository site
S Zare Ganjaroodi, S Hassanlou, A Maleki Farsani
Iranian Journal of Chemistry and Chemical Engineering, 2024
2024
Measurement of cesium and uranium distribution coefficient in the alluvial soil of Anarak disposal site using both Batch and column methods
AMF Saber Hassanlou, Saeed Zare Ganjaroodi
Environmental assessment and radiomonitoring, 2024
2024
Preoperational radiomonitoring program of near-surface disposal; A Case Study of Anarak Radioactive Waste Repository
AMF Saeed Zare Ganjaroodi, Mehdi Boroumandi, Hamireza Pakooyan
International conference on nuclear science and technology, 2024
2024
Thermoneutronic study of new generation TVS-2M fuel assemblies in Bushehr VVER-1000 reactor
EZ Saeed Zare Ganjaroodi
International conference on nuclear science and technology, 2024
2024
Neutron flux measurement in the Miniature Neutron Source Reactor using Mika nuclear track detector
EZ Saeed Zare Ganjaroodi, Nazaninzahra Raei, Javad Mokhtari
International conference on nuclear science and technology, 2024
2024
Operational safety assessment program for near-surface disposal; A Case Study of Anarak Repository
AMF Saeed Zare Ganjaroodi, Maryam Fani
International conference on nuclear science and technology, 2024
2024
Operational safety assessment program for near-surface disposal; A Case Study of Anarak Repository
International conference on nuclear science and technology, 2024
2024
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Articles 1–20