Yayınlar & Eserler

Makaleler 34
Tümü (34)
SCI-E, SSCI, AHCI (11)
SCI-E, SSCI, AHCI, ESCI (11)
Scopus (11)
TRDizin (19)
Diğer Yayınlar (4)

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BIO-MEDICAL MATERIALS AND ENGINEERING , sa.2, ss.1-2, 2017 (SCI-Expanded, Scopus)
Hakemli Bilimsel Toplantılarda Yayımlanmış Bildiriler 41

1. Improve or Approximation of Nuclear Reaction Cross Section Data Using Articial Neural Network

International Conference on Artificial Intelligence and Applied Mathematics in Engineering 2019, Türkiye, 20 - 22 Nisan 2019, cilt.43, ss.935-936, (Tam Metin Bildiri)

2. Approximation of Nuclear Reaction Cross Section Data Using Machine Learning Algorithm

6th International Conference on RecentAdvances in Pure and Applied Mathematics (ICRAPAM 2019), İstanbul, Türkiye, 12 - 15 Haziran 2019, cilt.1, ss.48-51, (Tam Metin Bildiri)

3. Analysis of Neutron Capture Cross Section

5th International Conference on Recent Advances in Pure and Applied Mathematics (ICRAPAM 2018), Türkiye, 23 - 27 Temmuz 2018, ss.91, (Tam Metin Bildiri)

4. Comparison of Bentonite and Sn Doped Bentonite Samples Under the Effects of Proton and Electron Irradiation

12th International Conference on Interaction of Radiation with Solids (IRS-2017), Minsk, Belarus, 19 - 22 Eylül 2017, ss.111-113, (Tam Metin Bildiri)

5. Investigation of Proton and Electron Irradiation Effects on Perlite and Different Rate Lead Containing Samples of Perlite

12th International Conference on Interaction of Radiation with Solids (IRS-2017), Misnk, Belarus, 19 - 22 Eylül 2017, ss.116-118, (Tam Metin Bildiri)

6. Investigation of Proton and Alpha Radiation Effects on Polymer Concrete by Using Geant4

12th International Conference on Interaction of Radiation with Solids (IRS-2017), Minsk, Belarus, 19 - 22 Eylül 2017, ss.98-100, (Tam Metin Bildiri)

7. Neutron Induced Reaction Cross-Section Calculations and Geant4 Simulation for the Fusion Reactor Material SiO2

12th International Conference on Interaction of Radiation with Solids (IRS-2017), 19 - 22 Eylül 2017, ss.89, (Tam Metin Bildiri)

9. Semi-Empirical Systematic Development for Photon Induced Nuclear Reaction Cross-Section Calculations

4th International Conference on Recent Advances in Pure and Applied Mathematics (ICRAPAM 2017), Kuşadası, Türkiye, 11 - 15 Mayıs 2017, ss.111, (Özet Bildiri)

10. A New Developed Semi-Empirical Formula for Nuclear Reaction Cross-Section Calculations

4th International Conference on Recent Advances in Pure and Applied Mathematics (ICRAPAM 2017), Kuşadası, Türkiye, 11 - 15 Mayıs 2017, ss.68, (Özet Bildiri)

11. Investigation of neutron and gamma induced reaction effects on TiO2 and Al2O3 coated nickel used at nuclear reactors

3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2017), Adana, Türkiye, 10 - 12 Mayıs 2017, ss.91, (Özet Bildiri)

12. Total cross–section calculations of neutron induced reactions for some control rod materials used in nuclear reactors

3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2017), Adana, Türkiye, 10 - 12 Mayıs 2017, ss.88, (Özet Bildiri)

13. (g,abs) cross–section calculations of some fusion structural materials

3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2017), Adana, Türkiye, 10 - 12 Mayıs 2017, ss.77, (Özet Bildiri)

14. (n,el) reaction cross-section calculations for some isotopes of Cd used as nuclear reactor control rod material

3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2017), Adana, Türkiye, 10 - 12 Mayıs 2017, ss.82, (Özet Bildiri)

15. Production cross–section calculations of medical Tb isotopes

3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2017), Adana, Türkiye, 10 - 12 Mayıs 2017, ss.90, (Özet Bildiri)

16. Nuclear Interaction Calculations for Al and B Reinforced Mylar by Using Geant4 Simulation Code

2nd International Turkic World Conference on Chemical Sciences and Technologies, üsküp, Makedonya, 26 - 30 Ekim 2016, (Özet Bildiri)

18. 177Lu Radyoizotopunun Üretim Tesir Kesiti Hesaplamaları

XI. Ulusal Nükleer Bilimler ve Teknolojileri Kongresi, Kuşadası, Türkiye, 12 - 14 Ekim 2016, ss.98, (Özet Bildiri)

19. Lu-177 Radyoizotopunun Üretim Tesir Kesiti Hesaplamaları

XI. Ulusal Nükleer Bilimler ve Teknolojileri Kongresi, Aydın, Türkiye, 12 - 14 Ekim 2016, ss.98, (Özet Bildiri)

20. Cross-Section Calculations of (g,xn) and (p,xn) Reactions for 197Au

1st International Underground Resources and Energy Conference, Yozgat, Türkiye, 6 - 08 Ekim 2016, ss.98, (Özet Bildiri)

21. Reaction Cross–Section Calculations of the Structural Reactor Materials 58,60,61,62,64Ni for Different Level Density Models

1st International Underground Resources and Energy Conference, Yozgat, Türkiye, 6 - 08 Ekim 2016, ss.47, (Özet Bildiri)

22. Cross Section Calculations of g xn and p xn Reactions for Au 197

1st International Underground Resources and Energy Conference, 6 - 08 Ekim 2016, (Özet Bildiri)

23. Effects of Mean Free Path Paremeters for Reaction Cross-Section Calculations

1st International Underground Resources and Energy Conference, Yozgat, Türkiye, 6 - 08 Ekim 2016, ss.94, (Özet Bildiri)

24. Production Cross-Section of Medical 177Lu Using Neutron and Proton Induced Reactions

1st International Underground Resources and Energy Conference, Yozgat, Türkiye, 6 - 08 Ekim 2016, ss.101, (Özet Bildiri)

25. Cross Section Computations of 238-242Pu Nuclei Used as Nuclear Fuel Recycle Material

2nd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2016), Hatay, Türkiye, 28 - 30 Nisan 2016, ss.39-43, (Tam Metin Bildiri)

26. Neutron Induced Cross-Section Calculations for 196,198,199,200Hg Isotopes

2nd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2016), Hatay, Türkiye, 28 - 30 Nisan 2016, ss.98, (Özet Bildiri)

27. Neutron Emission Spectra for 208Pb Target Nucleus

2nd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2016), Hatay, Türkiye, 28 - 30 Nisan 2016, ss.93-95, (Tam Metin Bildiri)

28. Geant4 Simulation of Nuclear Interactions for Some Polymers Used as Radiation Shielding Material

2nd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2016), Hatay, Türkiye, 28 - 30 Nisan 2016, ss.33-38, (Tam Metin Bildiri)

29. Cross Section Computations of 238-242Pu Nuclei Used as Nuclear Reactor Fuel Recycle Material

International Workshop on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2016), Hatay, Türkiye, 28 - 30 Nisan 2016, ss.39-43, (Tam Metin Bildiri)

30. LiH Reaktör Moderator Malzemesi İçin Hadronik Etkileşimlerin Geant4 Benzetimi

ADIM Fizik Günleri V, Eskişehir, Türkiye, 21 - 23 Nisan 2016, ss.120, (Özet Bildiri)

32. Nurse Exposure Doses Resulted From Bone Scintigraphy Patient

9th International Physics Conference of the Balkan-Physical-Union (BPU), İstanbul, Türkiye, 24 - 27 Ağustos 2015, cilt.1722, (Tam Metin Bildiri)

37. Radiation Effects Simulation of Some Polymers with Geant4 Used for Medical Purposes

International Workshop on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT2016), 28 - 30 Nisan 2015, (Özet Bildiri)

38. Comparison of Dose Distributions Calculated by the Cyberknife Monte Carlo and Ray Tracing Algorithms for Lung Tumors A Phantom Study

International Workshop on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT2015), 23 - 26 Nisan 2015, (Özet Bildiri)

39. Fission cross section calculations for Bi-209 target nucleus based on fission reaction models in high energy regions

International Workshop on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT), Osmaniye, Türkiye, 23 - 26 Nisan 2015, cilt.100, (Tam Metin Bildiri)

40. Geant4 calculations for space radiation shielding material Al2O3

International Workshop on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT), Osmaniye, Türkiye, 23 - 26 Nisan 2015, cilt.100, (Tam Metin Bildiri)

41. Gamma radiation exposure of accompanying persons due to Lu-177 patients

International Workshop on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT), Osmaniye, Türkiye, 23 - 26 Nisan 2015, cilt.100, (Tam Metin Bildiri) Sürdürülebilir Kalkınma
Metrikler

Yayın

75

Yayın (WoS)

16

Yayın (Scopus)

15

Atıf (WoS)

73

H-İndeks (WoS)

6

Atıf (Scopus)

82

H-İndeks (Scopus)

6

Atıf (Scholar)

25

H-İndeks (Scholar)

2

Atıf (TrDizin)

1

H-İndeks (TrDizin)

1

Atıf (Diğer Toplam)

1

Proje

4
BM Sürdürülebilir Kalkınma Amaçları