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Senem Senturk Lule
Title
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Cited by
Year
CFD simulations of hydrodynamics of conical spouted bed nuclear fuel coaters
S Şentürk Lüle, U Colak, M Koksal, G Kulah
Chemical Vapor Deposition 21 (4-5-6), 122-132, 2015
192015
The development of TM2-RIA code for TRIGA type research reactors
MA Allaf, SŞ Lüle, Ü Çolak
Annals of Nuclear Energy 145, 107545, 2020
42020
Application of CNUREAS and MCNP5 codes to VVER-1000 MOX Core Computational Benchmark
SŞ Lüle, L Özdemir, A Erdoğan
Progress in Nuclear Energy 85, 454-461, 2015
42015
The computational fluid dynamics evaluation of the diffuser on N-16 radioisotope rise time in TRIGA mark II research reactor tanks
S Bektaş, SŞ Lüle, Ü Çolak
Progress in Nuclear Energy 134, 103677, 2021
32021
The development of multi-physics approach with Monte Carlo and computational fluid dynamics coupling for reactor cores
F Kutbay, SŞ Lüle
Nuclear Engineering and Design 402, 112127, 2023
22023
An integrated method for atmospheric dispersion and corresponding risks: application to ITU TRIGA Mark II research reactor
S Bektaş, SŞ Lüle
Progress in Nuclear Energy 143, 104039, 2022
22022
Assessment of the detection efficiency calibration of high-resolution gamma-ray spectrometers by EGSnrc and MCNP6. 2 Monte Carlo codes
S Sayın, M Seferinoğlu, E Yeltepe, B Çetin, SŞ Lüle
Radiation Physics and Chemistry 203, 110601, 2023
12023
The Investigation of the Sensitivity of Monte Carlo Simulation Results to Modelling Approaches for Nuclear Reactor Cores
M ALLAF, SŞ LÜLE, Ü Çolak
Avrupa Bilim ve Teknoloji Dergisi, 110-115, 2022
12022
The Effect of Burnup on ITU TRIGA Mark II Research Reactor Control Parameters
FO Ozkan, SS Lule, U Colak
International Conference Nuclear Energy for New Europe, 2021
12021
Dose calculations of anthropomorphic voxel-based phantom for Americium-241/Beryllium neutron source
B SARIOĞLU, SŞ LÜLE, Ü ÇOLAK
BgNS Trans 25 (1), 81-85, 2020
12020
Criticality Analysis of Proposed TRIGA Spent Fuel Pit Design for Various Hypothetical Events
S Bektaş, SŞ Lüle, Ü Çolak
no. September, 2020
12020
Doppler Broadening Effect on Reactivity Feedback in ITU TRIGA MARK II Research Reactor
M Allaf, F Kutbay, SS Lule, U Colak
International Conference Nuclear Energy for New Europe, 2018
12018
Numerical investigation of behaviour of small modular molten salt reactor freeze plug under various reactor operating conditions
MC Kahraman, S Şentürk Lüle
Numerical Heat Transfer, Part A: Applications, 1-20, 2023
2023
FREEZE PLUG DESIGN IN MOLTEN SALT REACTOR WITH CONSIDERATION OF SOLIDIFICATION
MC Kahraman, SŞ Lüle, Ü Çolak
Техногенные системы и экологический риск, 13-15, 2021
2021
The Method to Predict First Critical Core Loading for Nuclear Reactors
SŞ LÜLE
Sakarya University Journal of Science 24 (6), 1329-1336, 2020
2020
Neutronic comparison of proposed claddings for accident tolerant fuel with Zirconium based cladding in PWRs
S Şentürk Lüle, Ü Çolak
BgNS Transactions 20 (2), 121-123, 2015
2015
Burnup calculations of TR-2 research reactor with monteburns Monte Carlo code
L Özdemir, A Erdoğan, S Şentürk Lüle
2012
Burnup calculations of TR-2 research reactor: MONTEBURNS simulations and experimental verifications
L Özdemir, A Erdoğan, S Şentürk Lüle
2010
THE COUPLED THERMO STRUCTURAL ANALYSIS OF TRIGA RESEARCH REACTOR FUEL ELEMENT
F Kutbay, SŞ LÜLE
Monte Carlo Analysis of Control Rod Worth for ITU TRIGA Mark II Research Reactor
F Özkan, M Allaf, S Şentürk Lüle, Ü Çolak
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Articles 1–20