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( Zafar ),김학용,박미라,박수진 한국공업화학회 2014 한국공업화학회 연구논문 초록집 Vol.2014 No.1
Crumpled-like TiO<sub>2</sub>-Pt/graphene nanocomposite was synthesized via a simple reflux strategy and employed as a simple capacitor electrode material. The composite was characterized by XRD, XPS, FESEM, HRTEM and the electrochemical properties were investigated by cyclic voltammetry (CV). Electrochemical characterization for introduced nanocomposite indicated that the corresponding specific capacitance is 160 F/g (at 5 mV/s) with good stability. The super electrochemical performance is recognized to the inorganic nanoparticle present on the composite and graphene distinct characteristics. To the best of our knowledge this is the first report on TiO<sub>2</sub>-Pt/graphene nanocomposite as an electrical double layer capacitor material.
( Zafar ),김태현 한국공업화학회 2017 한국공업화학회 연구논문 초록집 Vol.2017 No.1
There is a great importance in the development of anion exchange membrane fuel cells (AEMFCs) for renewable energy research. The high conductivity and stability under high pH conditions at elevated temperatures are required for AEMs. We report herein the partially cross-linked SEBSs as novel anion exchange membranes. The synthesis and properties of these newly developed AEMs will be discussed in detail.
( Zafar ),김태현 한국공업화학회 2018 한국공업화학회 연구논문 초록집 Vol.2018 No.0
There is a surge of interest in the development of anion exchange membrane fuel cells (AEMFCs) for renewable energy research. The high conductivity and stability under high pH conditions at elevated temperatures are required for AEMs. We report herein the tunable hydrophobic said chain SEBSs as novel anion exchange membranes. The synthesis and properties of these newly developed AEMs will be discussed in detail.
Embedded fission source approach to analyze external source effect in a subcritical reactor
Zafar, Zafar Iqbal,Kim, Myung Hyun Elsevier 2018 Nuclear engineering and design Vol.327 No.-
<P><B>Abstract</B></P> <P>A simple modification of the fission source spectrum is proposed for the Monte Carlo calculation for externally driven subcritical reactors. Embedded fission source (EFS) approach replaces the fission spectrum with the collective spectrum of the external source and fission working in a small region near to external source only. This model provides eigenvalue search with external source contribution resulting in direct connection with isotope depletion calculation within Monte Carlo simulation. MCNPX 2.6.0 is modified for EFS and tested for three kinds of reactor problems; critical fast reactor driven subcritical reactor, accelerator driven subcritical reactor and fusion-fission hybrid reactor. The effectiveness of the external sources is determined by the extra amount of the TRU isotopes burnt and increase in the core multiplication level. The tests were performed for two subcritical cases; <I>k<SUB>eff</SUB> </I> ∼ 0.986 and <I>k<SUB>eff</SUB> </I> ∼ 0.959, with initial TRU loading of 188.8 kg and 183.2 kg, respectively. The EFS approach is validated by simulating a fission source driven system which gave the multiplication factor comparable to the original MCNPX within one standard deviation (32 pcm). The difference in TRU burn-up for both subcritical cases is of the order of 0.1% for each driving neutron source option. The study showed that the EFS can be a simple and a reliable approximation for the external source analysis.</P> <P><B>Highlights</B></P> <P> <UL> <LI> An approximate technique, Embedded Fission Source model to account for the external source effect in a subcritical system. </LI> <LI> Philosophy and Mathematical basis of the EFS are explained. </LI> <LI> An algorithm to incorporate EFS into the MCNPX is introduced. </LI> <LI> Change in the multiplication factor caused by the external source is presented. </LI> <LI> The benefit of using harder neutron spectrum in transmutation of TRU isotopes is ascertained. </LI> </UL> </P>
Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing
Zafar Iqbal Zafar,박윤서,김명현 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.2
Use of the reconstructed fuel assemblies from partially burnt nuclear fuel pins is analyzed. This reutilizationoption is a potential candidate technique to make better use of the nuclear resources. Standardtwo step method is used to calculate node i.e. fuel assembly average burnup and then pin by pin h valuesare reconstructed to ascertain the residual reactivity in the used fuel pins. Fuel pins with h >1:0 are usedto reconstruct to-be-reused fuel assemblies. These reconstructed fuel assemblies are burnt during thecycle 3, 4, 5 and 6 of a 1000MWPWR core by replacing fresh, once burnt and twice burnt fuel assembliesof the reference core configurations. It is concluded that using reconstructed fuel assemblies for the freshfuel affect dearly on the cycle length (>50 EFPD) when more than 16 fresh fuel assemblies are replaced. However, this loss is less than 20 days if the number of fresh fuel assemblies is less than eight. For thecase of replacing twice burned fuel, cycle length could be increased slightly (10 days or so) providedburnt fuel pins from other reactors were also available. Reactor safety parameters, like axial off setð<±10%Þ, Doppler temperature coefficient ð <0Þ, moderator temperature coefficient at HFP ð <0Þ arealways satisfied. Though, 2D and 3D pin peaking factors are satisfied ð <1:55Þ and ð <2:52Þ respectively,for the cases using eight or less reconstructed fuel assemblies only