Determination of plutonium and uranium content and burnup using six group delayed neutrons
Nuclear Engineering and Technology, Vol. 51, Ocak 2019, s. 943-948, ISSN: 1738-5733
AKYÜREK TAYFUN, USMAN SHOAİB
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Review and characterization of best candidate isotopes for burnup analysis and monitoring of irradiated fuel
ANNALS OF NUCLEAR ENERGY, Vol. 69, Ocak 2014, s. 278-291, ISSN: 0306-4549
AKYÜREK TAYFUN, TUCKER LUCAS P, USMAN SHOAİB
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The Effect of Burnup on ITU TRIGA Mark II Research Reactor Control Parameters
International Conference on Nuclear Energy for New Europe, Bled/SLOVENYA, 6 Eylül 2021
ÖZKAN FADİME ÖZGE, ŞENTÜRK LÜLE SENEM, ÇOLAK ÜNER
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Effects of advanced fuel management strategies on fuel burnup
Fen Bilimleri Enstitüsü, Hacettepe Üniversitesi, 1999
BARIŞ SARIKAYA
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Monte Carlo neutronics and burnup calculations for pebble bed reactor
Fen Bilimleri Enstitüsü, Hacettepe Üniversitesi, 2005
GÜRDAL GÖKERİ
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Burnup Calculations of TR-2 Research Reactor: MONTEBURNS Simulations and Experimental Verifications
Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010, Tokyo/JAPONYA, 17 Ekim 2010
ÖZDEMİR LEVENT, ERDOĞAN ADEM, ŞENTÜRK LÜLE SENEM
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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
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Nuclear MOX Fuel Burnup Analysis and Monitoring Using Non Destructive Method
1st International Underground Resources and Energy Conference, YOZGAT/TÜRKİYE, 6 Ekim 2016, s. 2-2
AKYÜREK TAYFUN,USMAN SHOAİB
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Delayed fast neutron as an indicator of burn-up for nuclear fuel elements
Nuclear Engineering and Technology, Vol. 53, Ocak 2021, s. 3127-3132, ISSN: 1738-5733
AKYÜREK TAYFUN, SHOAİB SAİFULLAH B., USMAN SHOAİB
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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
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Burnup characteristics and performance of boron nitride and boron coated urania and urania gadolinia fuels
Nuclear Engineering and Design, Vol. 203, No. 1, Ocak 2001, s. 57-64, ISSN: 00295493
DURMAZUÇAR HASAN HÜSEYİN,ÇOLAK ÜNER,SARIKAYA BARIŞ,GÜNGÖR GÜNDÜZ
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Effect of burnup on the neutronic parameters of ITU TRIGA Mark II research reactor
Progress in Nuclear Energy, Vol. 83, Ağustos 2015, s. 26-34, ISSN: 01491970
TÜRKMEN MEHMET,ÇOLAK ÜNER,ERGÜN ŞULE
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