Yayınlar & Eserler

Yayın Ağı

SCI, SSCI ve AHCI İndekslerine Giren Dergilerde Yayınlanan Makaleler

Numerical investigation of behaviour of small modular molten salt reactor freeze plug under various reactor operating conditions

Şentürk Lüle S., Kahraman M. C.
NUMERICAL HEAT TRANSFER; PART A: APPLICATIONS , cilt.1, sa.1, ss.1-15, 2023 (SCI-Expanded)

Assessment of the detection efficiency calibration of high-resolution gamma-ray spectrometers by EGSnrc and MCNP6.2 Monte Carlo codes

Sayın S., Seferinoğlu M., Yeltepe E., Çetin B., Şentürk Lüle S.
Radiation Physics and Chemistry , cilt.203, 2023 (SCI-Expanded) identifier identifier

The development of multi-physics approach with Monte Carlo and computational fluid dynamics coupling for reactor cores

Kutbay F., Şentürk Lüle S.
Nuclear Engineering and Design , cilt.402, 2023 (SCI-Expanded) identifier identifier

Computational Fluid Dynamics Analysis of a Thermocline Thermal Storage Unit for Solar Thermal Applications

Şentürk Lüle S., Asaditaheri A.
ARABIAN JOURNAL FOR SCIENCE AND ENGINEERING , cilt.47, sa.7, ss.9005-9018, 2022 (SCI-Expanded) Sürdürülebilir Kalkınma identifier identifier

An integrated method for atmospheric dispersion and corresponding risks: Application to ITU TRIGA Mark II research reactor

Bektaş S., Şentürk Lüle S.
Progress in Nuclear Energy , cilt.143, 2022 (SCI-Expanded) identifier identifier

The computational fluid dynamics evaluation of the diffuser on N-16 radioisotope rise time in TRIGA mark II research reactor tanks

Bektaş S., Lüle S., Çolak Ü.
Progress in Nuclear Energy , cilt.134, 2021 (SCI-Expanded) identifier identifier

The development of TM2-RIA code for TRIGA type research reactors

Allaf M. A., Şentürk Lüle S., Çolak Ü.
ANNALS OF NUCLEAR ENERGY , cilt.145, 2020 (SCI-Expanded) identifier identifier

Application of CNUREAS and MCNP5 codes to VVER-1000 MOX Core Computational Benchmark

Lule S., OZDEMIR L., ERDOGAN A.
PROGRESS IN NUCLEAR ENERGY , cilt.85, ss.454-461, 2015 (SCI-Expanded) Sürdürülebilir Kalkınma identifier identifier

CFD simulations of hydrodynamics of conical spouted bed nuclear fuel coaters

Lule S., Çolak Ü., KÖKSAL M., KÜLAH G.
Chemical Vapor Deposition , cilt.21, sa.4-6, ss.122-132, 2015 (SCI-Expanded) identifier identifier

Diğer Dergilerde Yayınlanan Makaleler

Nükleer Emniyette Fiziksel Koruma Sistemi Tasarımı ve Analizi İçin Yerli Yazılım Geliştirilmesi

AKDEMİR M., ŞENTÜRK LÜLE S.
Savunma Bilimleri Dergisi , sa.42, ss.1-20, 2022 (Hakemli Dergi) identifier

Performance improvement methods for quartz tube solid particle fluidized bed solar receiver

Şentürk Lüle S., Bölük M.
Journal of Thermal Engineering , cilt.8, sa.4, ss.477-489, 2022 (ESCI) identifier identifier identifier

The Investigation of the Sensitivity of Monte Carlo Simulation Results to Modelling Approaches for Nuclear Reactor Cores

ŞENTÜRK LÜLE S., Allaf M., ÇOLAK Ü.
Avrupa Bilim ve Teknoloji Dergisi , sa.38, ss.110-115, 2022 (Hakemli Dergi)

Dose calculations of anthropomorphic voxel-based phantom for Americium-241/Beryllium neutron source

SARIOĞLU B., ŞENTÜRK LÜLE S., ÇOLAK Ü.
BgNS TRANSACTIONS , 2021 (Hakemli Dergi)

The Method to Predict First Critical Core Loading for Nuclear Reactors

Şentürk Lüle S.
Sakarya University Journal of Science , cilt.24, sa.6, ss.1248-1251, 2020 (Hakemli Dergi)

Neutronic Comparison of Proposed Claddings for Accident Tolerant Fuel with Zirconium Based Cladding in PWRs

ŞENTÜRK LÜLE S., ÇOLAK Ü.
BgNS TRANSACTIONS , cilt.20, sa.2, ss.121-123, 2015 (Hakemli Dergi)

Hakemli Kongre / Sempozyum Bildiri Kitaplarında Yer Alan Yayınlar

The Coupled Thermo Structural Analysis of TRIGA Research Reactor Fuel Element

KUTBAY F., ŞENTÜRK LÜLE S., ÇOLAK Ü.
The European Research Reactor Conference, Antwerp, Belçika, 16 Nisan 2023

Akışkan Yataklı Kurutucu ile Buğday Kurutmaya Yönelik İnce Tabakalı Kurutma Modellerinin İncelenmesi

ŞENTÜRK LÜLE S., DOĞAN A.
V. Ulusal Mühendislikte Bilimsel ve Mesleki Çalışmalar Kongresi, İstanbul, Türkiye, 16 Aralık 2022

Akışkan Yataklı Kurutucu Akış Hidrodinamiğinin Buğday Kurutma için Hesaplamalı Akış Dinamiği ile İncelenmesi

DOĞAN A., ŞENTÜRK LÜLE S.
V. Ulusal Mühendislikte Bilimsel ve Mesleki Çalışmalar Kongresi, İstanbul, Türkiye, 16 - 18 Aralık 2022

The Optimization of Fan Design In Totally Enclosed Type Induction Motor

ŞENTÜRK LÜLE S., Özyıldız T.
Başkent International Conference on Multidisciplinary Studies-III, Ankara, Türkiye, 23 - 25 Eylül 2022

Monte Carlo Estimation of Spent Fuel Gamma Spectrum and Dose from Measurement System

ŞENTÜRK LÜLE S., SARIOĞLU B., ÇOLAK Ü.
International Graduate Research Symposium, Türkiye, 1 - 03 Haziran 2022

Shielding Performance of a Proposed Spent Fuel Pit for the ITU TRIGA Mark II Research Reactor

BEKTAŞ S., ŞENTÜRK LÜLE S., ÇOLAK Ü.
European Research Reactor Conference, Helsinki, Finlandiya, 26 Eylül 2021

Computational Fluid Dynamics Analysis of ITU TRIGA Mark II Research Reactor Spent Fuel Pit

Sayın S., ŞENTÜRK LÜLE S., ÇOLAK Ü.
European Research Reactor Conference, Helsinki, Finlandiya, 26 Eylül 2021

Neutronic Analysis of Ventilated Dry Storage Cask with Monte Carlo Method

SARIOĞLU B., ŞENTÜRK LÜLE S., ÇOLAK Ü.
International Conference on Nuclear Energy for New Europe, Bled, Slovenya, 6 - 09 Eylül 2021

The Effect of Burnup on ITU TRIGA Mark II Research Reactor Control Parameters

ÖZKAN F. Ö., ŞENTÜRK LÜLE S., ÇOLAK Ü.
International Conference on Nuclear Energy for New Europe, Bled, Slovenya, 6 - 09 Eylül 2021

The application of Artificial Intelligence to Nuclear Power Plant Safety

Yavuz C., ŞENTÜRK LÜLE S.
30th International Joint Conference on Artificial Intelligence, Montreal, Kanada, 19 - 27 Ağustos 2021

Freeze Plug Design in Molten Salt Reactor with Consideration of Solidification

KAHRAMAN M. C., ŞENTÜRK LÜLE S., ÇOLAK Ü.
IV International (XVII Regional) Scientific Conference "Technogenic Systems and Environmental Risk", Obninsk, Rusya, 19 - 20 Nisan 2021, ss.13-15 Sürdürülebilir Kalkınma

CRITICALITY ANALYSIS OF PROPOSED TRIGA SPENT FUEL PIT DESIGN FOR VARIOUS HYPOTHETICAL EVENTS

Bektaş S., Şentürk Lüle S., Çolak Ü.
29th International Conference Nuclear Energy for New Europe, Piran, Slovenya, 7 - 10 Eylül 2020

The Role of Women in the Development of Effective Nuclear Risk Communication A Case Study by WiN Turkey

Göktepe G., Güngör N., Şentürk Lüle S., Songur E.
International Symposium on Communicating Nuclear and Radiological Emergencies to the Public, Vienna, Avusturya, 1 - 05 Ekim 2018 Sürdürülebilir Kalkınma

Monte Carlo Analysis of Control Rod Worth for ITU TRIGA Mark II Research Reactor

Özkan F. Ö., Allaf M., Şentürk Lüle S., Çolak Ü.
27th International Conference Nuclear Energy for New Europe, Piran, Slovenya, 10 - 13 Eylül 2018, ss.1

Doppler Broadening Effect on Reactivity Feedback in ITU TRIGA MARK II Research Reactor

Allaf M., Kutbay F., Şentürk Lüle S., Çolak Ü.
27th International Conference Nuclear Energy for New Europe, Piran, Slovenya, 10 - 13 Eylül 2018

The Future of Nuclear Energy and Changing Roles

Şentürk Lüle S., Çolak Ü.
International Energy Raw Materials and Energy Summit, İstanbul, Türkiye, 27 - 30 Eylül 2017, ss.1 Sürdürülebilir Kalkınma

The Future of Nuclear Energy and Changing Roles

ÇOLAK Ü., ŞENTÜRK LÜLE S.
İNERMA, Türkiye, 27 - 30 Eylül 2017

Thorium as Nuclear Fuel

ÇOLAK Ü., ŞENTÜRK LÜLE S.
İNERMA, 1 - 03 Ekim 2015

Accident Tolerant Fuel

ŞENTÜRK LÜLE S., ÇOLAK Ü.
İNERMA, 1 - 03 Ekim 2015

Application of Monte Carlo Techniques to Dose Rate Calculations of Gamma Irradiation Facility

ŞENTÜRK LÜLE S., ÇOLAK Ü.
23rd WiN Global Annual Conference, Avusturya, 24 - 27 Ağustos 2015

Nuclear Power projects in Turkey and Human Resource Development Activities

ÇOLAK Ü., ŞENTÜRK LÜLE S.
International Conference on Nuclear Human Resources Development in Asia and the Pacific, Malezya, 28 - 30 Ekim 2014 Sürdürülebilir Kalkınma

Assessment and Prognosis of Local Radioactive Incident Using Atmospheric Dispersion Modeling

Şimşek V., ŞENTÜRK LÜLE S.
International Conference on Global Emergency Preparedness and Response, Viyana, Avusturya, 19 - 23 Ekim 2015

Burnup Calculations of TR-2 Research Reactor with MONTEBURNS Monte Carlo Code

Özdemir L., erdoğan a., ŞENTÜRK LÜLE S.
International Conference Nuclear Science and Its Applications, Samarqand, Özbekistan, 25 Eylül 2012

Kitap & Kitap Bölümleri

The Application of Artificial Intelligence to Nuclear Power Plant Safety

Yavuz C., ŞENTÜRK LÜLE S.
Artificial Intelligence for Knowledge Management, Energy, and Sustainability, Eunika Mercier-Laurent,Gülgün Kayakutlu, Editör, Springer, ss.117-127, 2022

Reaktivite Geri Besleme

Çelik A., Tiftikçi A., Tanbay T., Çelikten O. Ş., Çelik N., Ayhan H., et al.
Nükleer Reaktör Fiziğinin Temelleri, Songül Karabulut Özen, Editör, Akademisyen, Ankara, ss.221-242, 2021

Metrikler

Yayın

42

Atıf (WoS)

22

H-İndeks (WoS)

1

Atıf (Scopus)

25

H-İndeks (Scopus)

3

Proje

10

Tez Danışmanlığı

7

Açık Erişim

1
BM Sürdürülebilir Kalkınma Amaçları