H. Yapici

发表

Performance of transition model for predicting low Re aerofoil flows without/with single and simultaneous blowing and suction

M. S. Genç, Unver Kaynak, H. Yapici, 2011 .

Investigation of the performance parameters and temperature distribution in fuel rod dependent on operation periods and first wall loads in fusion-fission reactor system fueled with ThO2

H. Yapici, O. İpek, M. Übeyli, 2003 .

Neutronic analysis of an ads fuelled with minor actinide and designed for spent fuel enrichment and fissile fuel production

H. Yapici, Busra Durmaz, Gizem Bakir, 2021, Nuclear Technology and Radiation Protection.

Neutronic Analysis of LBE-Uranium Spallation Target Accelerator Driven System Loaded with Uranium Dioxide in TRISO Particles

H. Yapici, S. Selçuklu, Gamze Genç, 2016 .

A comprehensive study on neutronics of a lead–bismuth eutectic cooled accelerator-driven sub-critical system for long-lived fission product transmutation

N. Demir, H. Yapici, Gamze Genç, 2008 .

On the Neutronic Performance of Hylife-II Reactor Fuelled with Carbide Fuels

H. Yapici, M. Übeyli, 2006 .

Rejuvenation of light water reactor spent fuel in fusion blankets

H. Yapici, S. Şahin, 1998 .

Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel

V. Ozceyhan, H. Yapici, S. Şahin, 2001 .

The Effect of Microporous Layer in Phosphoric Acid Doped Polybenzimidazole Polymer Electrolyte Membrane Fuel Cell

H. Yapici, Gamze Genç, Muhammet Çelik, 2013 .

Neutronic limits in infinite target mediums driven by high energetic protons

N. Demir, H. Yapici, Gamze Genç, 2007 .

NEUTRONIC LIMITS IN VARIOUS TARGET MEDIUMS DRIVEN BY A PROTON BEAM OF 1 GeV ENERGY

H. Yapici, Gamze Genç, 2007 .

POTENTIAL OF A CATALYZED (D,D) FUSION-DRIVEN HYBRID REACTOR FOR THE REGENERATION OF LWR SPENT FUEL

Nafiz Kahraman, Hüseyin Yapıcı, S. Orhan Akansu, 2011 .

Potential of a Catalyzed Fusion-Driven Hybrid Reactor for the Regeneration of Candu Spent Fuel

E. Baltacioǧlu, H. Yapici, S. Şahin, 1991 .

Investigation of the Neutronic Potential of Moderated and Fast (D,T) Hybrid Blankets for Rejuvenation of CANDU Spent Fuel

H. Yapici, S. Şahin, 1989 .

CALCULATIONS OF MAXIMUM TEMPERATURE IN CENTERLINE OF NUCLEAR FUEL ROD AND FISSILE FUEL ENRICHMENT IN HYBRID REACTOR

V. Ozceyhan, S. Demirel, H. Yapici, 2004 .

Power flattening of an inertial fusion energy breeder with mixed ThO2–UO2 fuel

Hüseyin Yapıcı, H. Yapici, 2003 .

Temperature distribution in mixed ThO2–UO2 fuel rods located in blanket of an inertial fusion energy breeder

H. Yapici, 2002 .

Neutronic analysis of PROMETHEUS reactor fueled with various compounds of thorium and uranium

H. Yapici, M. Übeyli, S. Yalçin, 2002 .

Neutronic analysis of an inertial fusion energy breeder with SiCf/SiC

V. Ozceyhan, H. Yapici, 2002 .

Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D–T) driven hybrid reactor system

H. Yapici, 2001 .

Neutronic performance of proliferation hardened thorium fusion breeders

H. Yapici, S. Şahin, N. Şahi̇n, 2001 .

Spent mixed oxide fuel rejuvenation in fusion breeders

M. Bayrak, H. Yapici, S. Şahin, 1999 .

Neutronic analysis of a thorium fusion breeder with enhanced protection against nuclear weapon proliferation

H. Yapici, S. Şahin, 1999 .

Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

H. Yapici, S. Selçuklu, Gizem Bakir, 2016 .

Time-Dependent Neutronic and Burn-up Analyses of in a Thorium-Based ADS cooled with Various Coolants

H. Yapici, Gizem Bakir, 2017 .

Time-Dependent Neutronic Analysis of a Power-Flattened Gas Cooled Accelerator Driven System Fuelled with Thorium, Uranium, Plutonium, and Curium Dioxides TRISO Particles

Hüseyin Yapıcı, Gamze Genç, Gizem Bakır, 2016 .

Neutron-Induced Medical Radioisotope Production in a Conceptual Accelerator-Driven System, Fueled with Uranium Carbide

H. Yapici, S. Selçuklu, Gamze Genç, 2016 .

Integral data for most important materials, namely lithium, beryllium, lead and uranium in infinite medium per fusion neutron

V. Ozceyhan, H. Yapici, 2004 .

Integral data for incident fusion source neutrons in infinite medium

V. Ozceyhan, H. Yapici, O. İpek, 2002 .

Numerical solutions of conjugate heat transfer and thermal stresses in a circular pipe externally heated with non-uniform heat flux

Hüseyin Yapıcı, H. Yapici, Bilge Albayrak, 2004 .

Numerical solutions of transient temperature and thermally induced stress distributions in a solid disk heated with radially periodic expanding and contracting ring heat flux

Hüseyin Yapıcı, H. Yapici, Gamze Baştürk, 2005 .

Numerical solutions of transient conjugate heat transfer and thermally induced stress distribution in a heated and rotating hollow disk

Hüseyin Yapıcı, H. Yapici, Gamze Baştürk, 2005 .

The effects of temperature on transport phenomena in phosphoric acid doped polybenzimidazole polymer electrolyte membrane fuel cell

Hüseyin Yapıcı, Muhammet Çelik, Gamze Genç, 2016 .

Numerically Modeling of Anode Supported Tubular SOFC

M. Kaya, N. Demir, H. Yapici, 2013 .

Study on transmutation of minor actinides discharged from high burn-up PWR-MOX spent fuel in the force-free helical reactor

H. Yapici, 2003 .

Transmutation–incineration potential of transuraniums discharged from PWR-UO2 spent fuel in modified PROMETHEUS fusion reactor

N. Demir, H. Yapici, Gamze Genç, 2006 .

Study of fissile fuel breeding concept for the force-free helical reactor

H. Yapici, 2003 .

Determination of the optimal plutonium fraction in transuranium discharged from pressured water reactor (PWR) spent fuel for a flat fission power generation in the force-free helical reactor (FFHR) along the transmutation period

H. Yapici, 2003 .

Transient thermal stress distribution in a circular pipe heated externally with a periodically moving heat source

H. Yapici, M. Genç, Gülşah Özişik, 2012 .

Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System

H. Yapici, Gizem Bakir, A. B. Arslan, 2019, Science and Technology of Nuclear Installations.

Numerical calculation of local entropy generation in a methane–air burner

Hüseyin Yapıcı, H. Yapici, Gamze Baştürk, 2005 .

Investigation of neutronic potential of a moderated (D–T) fusion driven hybrid reactor fueled with thorium to breed fissile fuel for LWRs

M. Bayrak, H. Yapici, N. Şahi̇n, 2000 .

Neutronic performance of coupled hybrid blanket fueled with ThO2 and UO2

Hüseyin Yapıcı, Osman Ipek, H. Yapici, 2003 .

Study on transient local entropy generation in pulsating fully developed laminar flow through an externally heated pipe

Nafiz Kahraman, Hüseyin Yapıcı, N. Kahraman, 2006 .

Numerical study on transient local entropy generation in pulsating turbulent flow through an externally heated pipe

H. Yapici, Gamze Baştürk, Hüseyİn Yapici, 2005 .

Numerical Study On Local Entropy Generation In Compressible Flow Through A Suddenly Expanding Pipe

Nafiz Kahraman, Hüseyin Yapici, Gamze Bastürk, 2005, Entropy.

Numerical study on conjugate heat transfer in laminar fully developed flow with temperature dependent thermal properties through an externally heated SiC/SiC composite pipe and thermally induced stress

Hüseyin Yapıcı, H. Yapici, Gamze Baştürk, 2005 .

Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor

H. Yapici, Busra Durmaz, Gizem Bakir, 2022, Nuclear Technology and Radiation Protection.

Hydrogen production via water splitting process in a molten-salt fusion breeder

N. Demir, H. Yapici, M. Übeyli, 2010 .

Rejuvenation of spent fuel in the force-free helical reactor (FFHR)

Murat Gökçek, H. Yapici, 2005 .

Rapid Transmutation of High-Level Nuclear Wastes in a Catalyzed Fusion-Driven System

N. Demir, H. Yapici, Gamze Genç, 2009 .

Time-dependent Neutronic Analysis for High Level Waste Transmutation in a Fusion-driven Transmuter

N. Demir, H. Yapici, Gamze Genç, 2008 .

Modification of PROMETHEUS Reactor as a Fusion Breeder and Fission Product Transmuter

H. Yapici, Gülşah Özişik, 2008 .

Neutronic Analysis for Transmutation of Minor Actinides and Long-Lived Fission Products in a Fusion-Driven Transmuter (FDT)

N. Demir, H. Yapici, Gamze Genç, 2006 .

TRANSMUTATION OF HIGH LEVEL WASTES IN A FUSION-DRIVEN TRANSMUTER (FDT)

H. Yapici, Gamze Genç, 2007 .

ANAL Y SIS OF FUEL RE JU VE NA TION TIMES IN A FU SION BREEDER RE AC TOR FU ELLED WITH A MIX TURE OF URA NIUM-THO RIUM OX IDES FOR THE CANDU RE AC TOR

H. Yapici, Gizem Bakir, 2017 .

STUDY OF A CON CEP TUAL AC CEL ER A TOR DRIVEN SYS TEM LOADED WITH THO RIUM DI OX IDE MIXED WITH TRANS URANIC DI OX IDES IN TRISO PAR TI CLES

H. Yapici, Gamze Genç, Gizem Bakir, 2016 .

Power flattening in Prometheus breeder reactor using nuclear fuel and waste actinide

H. Yapici, M. Übeyli, 2003 .

Study on spent fuel rejuvenation in PROMETHEUS fusion reactor

B. Çeper, N. Demir, H. Yapici, 2006 .

Neutronic analysis of denaturing plutonium in a thorium fusion breeder and power flattening

M. Bayrak, H. Yapici, 2005 .

Fusion breeder with enhanced safeguarding capabilities against nuclear weapon proliferation

E. Baltacioǧlu, H. Yapici, S. Şahin, 1998 .

Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blancket

E. Baltacioǧlu, H. Yapici, S. Şahin, 1994 .

Neutronic analysis of a moderated (D, T) fusion driven hybrid blanket

V. Ozceyhan, S. Akansu, H. Yapici, 2000 .

Analysis of the rejuvenation performance of hybrid blankets by using uranium fuels (UN, UC, UO2, U3Si2) and different coolants for various volume fraction

V. Ozceyhan, H. Yapici, O. İpek, 2000 .

Heavy water reactor spent-fuel regeneration with fusion neutrons

E. Baltacioǧlu, H. Yapici, S. Şahin, 1989 .

Non-uniform temperature gradients and thermal stresses produced by a moving heat flux applied on a hollow sphere

H. Yapici, M. Serdar Genç, Gülşah Özişik, 2010 .

Reduction of thermally induced stress in a solid disk heated with radially periodic expanding and contracting ring heat flux

Hüseyin Yapıcı, H. Yapici, Gamze Baştürk, 2006 .

Transient temperature and thermally induced stress distributions in a partly-circumferentially heated cylindrical workpiece

H. Yapici, S. Yalçin, 2004 .

Utilization of Heavy Metal Molten Salts in the ARIES-RS Fusion Reactor

H. Yapici, M. Übeyli, 2008 .