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Toplam 47 adet sonuçtan 20 tanesi görüntülenmektedir.

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Spent fuel interrogation using delayed fast neutron spectrum at Missouri University of Science and Technology Reactor
PROGRESS IN NUCLEAR ENERGY, Vol. 85, Ocak 2015, s. 525-540, ISSN: 0149-1970
AKYÜREK TAYFUN, USMAN SHOAİB
Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, Vol. 321, Ocak 2019, s. 109-116, ISSN: 0236-5731
ALBARQİ MUBARAK, ALSULAMİ RAED, AKYÜREK TAYFUN, GRAHAM JOSEPH
Histopathological Analysis of the Liver Tissue Across Different Cytotypes of the Blind Mole Rat: Nannospalax xanthodon
6th International Conference on Materials Science and Nanotechnology For Next Generation (MSNG2019), Niğde/TÜRKİYE, 16 Ekim 2019, s. 167
BİTERGE SÜT BURCU,İKİNCİ KELEŞ AYŞE,KANKILIÇ TEOMAN
Numerical modelling of groundwater radionuclide transport with finite difference-based method of lines
Journal of Radioanalytical and Nuclear Chemistry (Springer Science and Business Media LLC), Vol. 332, No. 11, Temmuz 2023, s. 4833-4845, ISSN: 0236-5731
TANBAY TAYFUN, DURMAYAZ AHMET
Interference Corrections for Some Spectral Peaks Used in Gamma Spectrometric Analysis of 238U and 226Ra in Presence of Thorium in Samples
The Fifth Eurasian Conference on Nuclear Science and Its Application, 14 Ekim 2008, s. 79
YÜCEL HALUK, UYAR ESRA, ESEN AYŞE NUR, BOR MEHMET DOĞAN
Ayşe Nur Esen Özet Bildiri
Comparison of the Activity Results Measured in the well-type HPGe Detector by Using Radionuclide Specific and Absolute Efficiency Calibrations
The Fifth Eurasian Conference on Nuclear Science and Its Application, 14 Ekim 2008, s. 77
ESEN AYŞE NUR, YÜCEL HALUK, UYAR ESRA, BOR MEHMET DOĞAN
Ayşe Nur Esen Özet Bildiri
Clustering Dynamic PET Images on the Projection Domain
IEEE Transactions on Nuclear Science, Vol. 54, No. 3, Haziran 2007, s. 496-503, ISSN: 0018-9499
BAYRAKTAR BÜLENT,KAMAŞAK MUSTAFA ERSEL
Mustafa Ersel Kamaşak Özgün Makale
n a reaction Cross section of 44Ca 45Sc 51V Nuclei from 13 6 to 14 9 MeV Neutron Energies
NUCLEAR SCIENCE AND ENGINEERING, Vol. 130, No. 2, Ekim 1998, s. 254-260, ISSN: 0029-5639
SUBAŞI M,ERDURAN MUSTAFA NİZAMETTİN,BOSTAN İSMAİL MELİH,REYHANCAN İSKENDER ATİLLA,GÜLTEKİN E,TARCAN G
O 16 n p N 16 reaction cross sections around 14 MeV
Nuclear Science and Engineering, Vol. 135, No. 3, Temmuz 2000, s. 260-266
SUBAŞI M,GÜLTEKİN E,REYHANCAN İSKENDER ATİLLA
Measurements of Isomeric Cross Sections for n Reaction on 144Sm Isotope for Neutrons Around 14 MeV
Nuclear Science and Engineering, Vol. 174, No. 2, Haziran 2013, s. 202-207, ISSN: 00295639
REYHANCAN İSKENDER ATİLLA,DURUSOY AYŞE
Effects of the Coagulation Bath and ReductionProcess on SO2 Adsorption Capacity of GrapheneOxide Fiber
World Academy of Science, Engineering and Technology ,International Journal of Chemical, Molecular, Nuclear, Materials and Metallurgical Engineering, Vol. 11, No. 6, Ağustos 2017, s. 375-378
ALPTOĞA ÖZGE,UÇAR NURAY,YAVUZ NİLGÜN,ÖNEN HACER AYŞEN
Hacer Ayşen Önen Özgün Makale
Calculation of radiation doses due to release of 137 Cs and 131 I using atmospheric dispersion and dose calculation models
Nuclear Science and Its Application, Samarkand/ÖZBEKİSTAN, 6 Ekim 2014
ŞİMŞEK VOLKAN,KINDAP TAYFUN,ÜNAL ALPER,POZZOLİ LUCA,KARACA MEHMET
Alper Ünal Özet Bildiri
Burnup Calculations of TR-2 Research Reactor with MONTEBURNS Monte Carlo Code
International Conference Nuclear Science and Its Applications, Samarkand/ÖZBEKİSTAN, 25 Eylül 2012
ÖZDEMİR LEVENT, ERDOĞAN ADEM, ŞENTÜRK LÜLE SENEM
Senem Şentürk Lüle Özet Bildiri
Multi physics Analysis of Spherical Fast Burst Reactors
Nuclear Science and Engineering(NSE), Vol. 163, 2009, s. 132-143
KADIOĞLU SAMET YÜCEL,KNOLL DANA,OLİVEİRA CASSİANO
Samet Yücel Kadıoğlu Özgün Makale
Role of Polymer-Based Barrier Systems in Exposed Dose of Biota through Tin from Redox-Sensitive Elements in Nuclear Waste
International Symposium on Academic Studies in Science, Engineering and Architecture Studies, 15 Kasım 2019
İLERİ RÜVEYDA KÜBRA,ERENTÜRK SEMA
Sema Erentürk Tam metin bildiri
Monte Carlo criticality calculations for a pebble bed reactor with MCNP
Nuclear Science and Engineering, Vol. 149, 2005, s. 131-137, ISSN: 0029-5639
ÇOLAK ÜNER,ŞEKER VOLKAN
Thermodynamic analysis of a nuclear desalination cogeneration plant
22nd Congress on Thermal Science and Technology, Kocaeli/TÜRKİYE, 11 Eylül 2019, s. 415-420
ŞEKERCİ HÜSEYİN,DEMİR ERCAN,TANBAY TAYFUN,DURMAYAZ AHMET
Ahmet Durmayaz Tam metin bildiri
Simulation of 137Cs transport and deposition after the Chernobyl Nuclear Power Plant accident and radiological doses over the Anatolian Peninsula
Science of The Total Environment, Vol. 499, Kasım 2014, s. 74-88, ISSN: 00489697
SİMSEK VOLKAN,POZZOLİ LUCA,ÜNAL ALPER,KINDAP TAYFUN,KARACA MEHMET
Alper Ünal Özgün Makale
Investigation of the 6Li(p,?) 7Be Reaction at Low Energies
4. Eurasian Conference On Nuclear Science and Its Application, 2006, s. 141-145
BAYKAL A., REYHANCAN I.A., ELMALI A., OZBIR Y., ERDURAN M.N.
(n,?) reaction Cross-section of 44Ca, 45Sc, 51V Nuclei from 13.6 to 14.9 MeV Neutron Energies
Nuclear Science and Engineering, No. 130, 1998, s. 254-260
SUBASI M, ERDURAN M.N., BOSTAN M., REYHANCAN I.A., GULTEKIN E., TARCAN G, OZBIR Y.

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