Min Ku Jeon

• PhD
• Principal Investigator at Korea Atomic Energy Research Institute

The accumulation of dry active wastes such as latex gloves in nuclear facilities has become a serious issue because of the high cost and limited storage area for their management. In this study, the liquefaction of latex gloves, which mainly comprise rubber and CaCO3, was investigated as a waste reduction technique. When liquefaction occurred at >...

The accumulation of dry active wastes (DAWs) such as latex gloves in nuclear facilities has become a serious issue because of the high cost and limited storage area for their management. In this study, the liquefaction of latex gloves, which mainly comprise rubber and CaCO 3 , was investigated as a waste reduction technique. When liquefaction occur...

Radionuclide-contaminated concrete can be turned into non-radioactive industrial waste through the sequential application of thermomechanical and chemical treatments. Herein, we examine the removal of 137Cs, 90Sr, and 60Co from complex acidic wastewater generated by chemical treatment, revealing that wastewater radioactivity due to these nuclides c...

Dry active wastes (DAWs) are a type of combustible radioactive solid waste, which includes decontamination paper, protective clothing, filters, plastic bags, etc. generated from operating nuclear facilities and decommissioning projects. The volume of DAWs could be increased over time, disadvantage to higher disposal costs and space utilitization of...

The lithium extraction method, involving the chlorination of unevenly degraded spent cathodes, successfully upcycled a Ni-rich single-crystalline cathode material that exhibited excellent performance, especially in bimodal electrodes.

A chlorination technique was investigated as an option for the decontamination of radioactive concrete waste, which is one of the most common types of wastes generated during the decommissioning of nuclear power plants. Simulated concrete waste that includes target nuclides of Co, Sr, and Cs was utilized to evaluate the removal efficiency of each n...

The chlorination behavior of Li(Ni0.6Co0.2Mn0.2)O2 (NCM(622)), a cathode material for Li-ion batteries, was investigated. Chlorination experiments were conducted in the temperature range of 400–600 ℃ for 1, 2, 4, and 8 h at each temperature under a 190 mL/min Ar + 10 mL/min Cl2 flow. A gradual phase transition from 1) a layered hexagonal structure...

Decommissioning waste is generated at all stages during the decommissioning of nuclear facilities, and various types of radioactive waste are generated in large quantities within a short period. Concrete is a major building material for nuclear facilities. It is mixed with aggregate, sand, and cement with water by the relevant mixing ratio and drie...

The recycling of Li(Ni1/3Co1/3Mn1/3)O2 (NCM) and LiCoO2 (LCO), which are cathode materials for Li-ion batteries, was demonstrated via a chlorination-based Li extraction technique. The recycling process follows a chlorination - washing/filtering - drying - mixing - re-synthesis process. Around 86% of Li was removed through the chlorination - washing...

CaCO3 powder containing C-14, which has a long half-life, is generated from the treatment process of spent activated carbons from the air cleaning system in a nuclear facility, can be decomposed into CaO and CO2 gas at a temperature above 600 °C. This CaCO3 must be fabricated into a stable waste form for final disposal at a temperature below 600 °C...

Radioactively contaminated metal components are generated during the operation or decommissioning of a nuclear power plant. These metals can be effectively decontaminated using a foam containing H2SO4 and Ce(IV) with significant reduction of radioactive liquid wastes. However, this decontamination method generates strong acidic wastewater containin...

The chlorination behavior of Li(Ni1/3Co1/3Mn1/3)O2 (NCM) was investigated as a function of the reaction temperature (400–600 °C) and time (1–8 h) for application in a chlorination-based recycling process. Structural analysis results revealed that chlorination leads to a sequential transition from a hexagonal LiMO2 structure to a hexagonal Li1−x′MO2...

The chlorination behavior of LiCoO2 (LCO) was investigated as a function of the reaction temperature (400–600 °C) and time (1–8 h) under a 190 mL/min Ar+10 mL/min Cl2 flow. Based on the results of a structural analysis, a sequential reaction mechanism was proposed for the chlorination of LCO: LiCoO2→(400–600 °C) Li1−xCoO2−y→(450–600 °C) Co3O4→ (500...

A new approach to recycle Li(Ni,Co,Mn)O2 (NCM, Ni:Co:Mn=1:1:1) is introduced and experimentally demonstrated. Chlorine gas was employed as a reaction agent to selectively extract Li from NCM. Through a reaction at 550 °C for 4 h under a 180 mL/min Ar+20 mL/min Cl2 flow, Li was converted into water-soluble LiCl, while the initial transition metals (...

Concrete is one of the largest wastes, by volume, generated during the decommissioning of nuclear facilities, which significantly influences the projected costs for the disposal of decommissioning wastes. Concrete consists of aggregates and a cement binder. In radioactive concrete the radioisotopes are mainly associated with the cement component. I...

Considering the necessity of the development of methods to reduce the burden of storage and disposal of high-level radioactive waste, in this study, we propose a nuclide separation technique using molten salt immersion. The dissolution behavior of simulated spent nuclear fuels (SSFs) immersed in a LiCl-KCl-UCl3 (LKU) molten salt at 500°C was invest...

Extracting cesium (Cs) from nonexpandable illite clay is important in the remediation of radioactive Cs-contaminated soil. In this study, we investigated a chloride salt treatment technique for the removal of Cs from illite. Cs-loaded illite samples with initial Cs concentrations of 2430 and 690 ppm were treated using a NaCl–MgCl2–CaCl2 ternary sal...

Solid-state mechanochemical reduction combined with subsequent melting consolidation was suggested as a technical op-tion for the oxide reduction in pyroprocessing. Ni ingot was produced from NiO as a starting material through this technique while Li metal was used as a reducing agent. To determine the technical feasibility of this approach for pyr...

The feasibility of the chlorination reaction as a decontamination technique for 90Sr-contaminated concrete waste was investigated via thermodynamic and experimental approaches. Thermodynamic calculations suggested that SrO reacts with chlorine prior to CaO, CaCO3, and MgO, while other oxides remain in their oxide forms. It was found experimentally...

The electrochemical behavior of CsI in LiCl molten salt was investigated to identify its impact on the electrolytic oxide reduction of oxide-phase spent nuclear fuels by combined electrolysis and cyclic voltammetry experiments of LiCl-CsI in comparison with LiCl, LiCl-CsCl, and LiCl-LiI. It was found that Cs⁺ ions were hardly involved in the cathod...

This study explored the feasibility of rinsing a metallic fuel in a separate LiCl salt as a new alternative to salt distillation, aimed to dilute Li and Li2O in the residual oxide reduction (OR) salt of the fuel and then supply the fuel for electrorefining. The rinsed metallic fuel was conducted by simply immersing the fuel in a LiCl salt at 650 °C...

Ba and Sr elements in spent nuclear fuels are supposed to accumulate in LiCl molten salt electrolyte by forming chlorides (i.e., BaCl2, SrCl2) during oxide reduction in pyroprocessing. An electrochemical examination was performed in a LiCl–BaCl2–SrCl2 system to identify the effect of the BaCl2 and SrCl2 on the C anode-based oxide reduction process....

Residual salt separation is an essential step in pyroprocessing because its reaction products, as prepared by electrochemical unit processes, contain frozen residual electrolyte species, which are generally composed of alkali-metal chloride salts (e.g., LiCl, KCl). In this study, a simple technique that utilizes high-temperature gas flux as a drivi...

Chemical stabilities of SrZrO3, BaZrO3, and Sr0.5Ba0.5ZrO3 in LiCl molten salt were investigated to evaluate dissolution properties of Sr and Ba in grey phases of spent nuclear fuels during oxide reduction. Sr in SrZrO3 was partially insoluble in LiCl, even in the presence of metallic Li, while Ba in BaZrO3 was almost extracted. In contrast, both S...

A quantitative analysis on the behavior of rare earth (RE) oxides during the electrolytic reduction process was conducted through thermodynamic calculations. The calculation results can identify the oxide form of RE elements as RE2O3 including Ce and Pr, and provide a quantitative explanation on the slow reduction of RE oxides, compared to UO2, as...

Pyroprocessing uses various molten salts during electrochemical unit processes. Reaction products after the electrochemical processes must contain a significant amount of residual salts to be separated. Vacuum distillation is a common method to separate the residual salts; however, its high operation temperature may cause side reactions. In this st...

The widespread use of Pt anodes in pyroprocessing for oxide reduction inspired us to investigate the stability of a representative Pt anode in repeated UO2 reduction experiments. The formation and subsequent exfoliation of an oxide layer on the Pt surface was shown to result in anode degradation, decreasing the electrode thickness from 2 to 1.22 mm...

We report that residual salt removal by high-temperature distillation causes partial reoxidation of uranium metal to uranium oxide in electrolytically reduced simulated oxide fuel. Specifically, the content of uranium metal in the above product decreases with increasing distillation temperatures, which can be attributed to reoxidation by Li2O conta...

Finding technical issues associated with equipment scale-up is an important subject for the investigation of pyroprocessing. In this respect, electrolytic reduction of 1 kg-UO2, a unit process of pyroprocessing, was conducted using graphite as an anode material to figure out the scale-up issues of the C anode-based system at pilot-scale. The graphi...

Reoxidation reaction of metallic uranium in the oxide reduction system for pyroprocessing of used nuclear fuels is quantitatively investigated via calculating thermodynamic equilibrium compositions. The calculations consider three operating parameters; LiCl/U ratio, Li2O concentration, and excess metallic Li. The results suggest that decreasing LiC...

Ten electrolytic reduction or oxide reduction (OR) runs of a 0.6 kg scale-simulated oxide fuel in a Li2O-LiCl molten salt at 650 °C were conducted using metal anode shrouds. During this procedure, an anode shroud surrounds a platinum anode and discharges hot oxygen gas from the salt to outside of the OR apparatus, thereby preventing corrosion of th...

We present our findings that uranium (U) metal prepared by using the electrolytic reduction process for U oxide (UO2) in a Li2O–LiCl salt can be reoxidized into UO2 through the reaction between the U metal and Li2O in LiCl. Two salt types were used for immersion of the U metal: one was the salt used for electrolytic reduction, and the other was app...

Estimation of centerline temperature of nuclear glass waste form for each waste stream is very essential in the period of storage because the centerline temperature being over its glass transition temperature results in the increase of leaching rate of radioactive nuclides due to the devitrification of glass waste form. Here, to verify the effects...

As a process improvement, the distillation and recovery of the salts used in UO2 electrolytic reduction is required. The basic characteristics of the distillation of a LiCl–Li2O electrolyte containing UO2 pellets were investigated. UO2 pellets were immersed in LiCl–Li2O (1.0 wt%) and the mixture was subjected to distillation at 930–740 °C under Ar...

In this study, the feasibility of yttria-stabilized zirconia (YSZ) was investigated for use as a ceramic material, which can be commonly used for both electrolytic reduction and electrorefining. First, the stability of YSZ in salts for electrolytic reduction and electrorefining was examined. Then, its stability was demonstrated by a series of pyrop...

The electrolytic reduction rate of porous UO2 pellets in a LiCl salt was investigated for various applied charges. The degree of reduction (α) value was evaluated from the ratios of cross-sectional areas of the reduced and oxide parts. An analysis of the experimental results revealed that the first-order reaction model is the best geometry function...

PtSn/C and Pt5Sn4M/C (M = W, Pd, Ni) electrocatalysts were prepared by impregnation method using NaBH4 as a reducing agent. Chemical composition, crystalline size, and alloy formation were determined by EDX, XRD and TEM. The average particle sizes of the synthesized catalysts were approximately 3.64∼4.95 nm. The electro-chemical properties were mea...

Carbon was investigated as an anode material for electrolytic reduction in pyroprocessing. UO2 was successfully reduced to U repeatedly using the carbon anode and the LiCl molten salt could be reused. While reusing the molten salt with a carbon anode is difficult under normal conditions (~3 V) due to Li2CO3 formation, applying a high voltage (>10 V...

Conductive ceramics are being developed to replace current Pt anodes in the electrolytic reduction of spent oxide fuels in pyroprocessing. While several conductive ceramics have shown promising electrochemical properties in small-scale experiments, their long-term stabilities have not been investigated yet. In this study, the chemical stability of...

A new process to co-recover uranium and transuranic nuclides from used nuclear fuels was introduced, which was named ‘MKZP’ (Min Ku Zirconium Process), as an alternative of widely known pyroprocessing. Instead of an electrochemical reduction of the pyroprocessing, the MKZP employs Zr and ZrCl4 as reactants to chemically convert U3O8 into UCl3, whic...

A thermo-gravimetric analysis system for hull chlorination reaction (TGA-HC) was employed to measure weight change of ZIRLO cladding hulls in-situ during the chlorination reaction. The total flow rate (Q) experiments suggested that the chlorination reaction of ZIRLO is within the gas phase transport limited region for Q of 120 and 240 mL/min condit...

A commercially available copper mesh was investigated as an iodine off-gas capturing medium for pyroprocessing, with an aim to replace costly silver based adsorbents. Theoretical calculation results suggested that the reaction between metallic copper and gaseous iodine will occur spontaneously to produce copper iodide in the temperature range of 10...

The reaction rates of ZIRLO cladding hulls with cross-section openings were investigated using a thermo-gravimetric analysis system in order to identify whether selective recovery of Zr from oxidized cladding hulls is possible. The experimental results showed that an oxidized ZIRLO cladding hull was not reactive with chlorine gas at 400℃. However,...

The platinum anode for the electrolytic reduction process is generally surrounded by a nonporous ceramic shroud with an open bottom to offer a path for O_2 gas produced on the anode surface and prevent the corrosion of the electrolytic reducer. However, the O^{2-} ions generated from the cathode are transported only in a limited fashion through the...

Used cladding hulls from pressurized water reactor (PWR) are characterized to provide useful information for the treatment and disposal of cladding hull wastes. The radioactivity and the mass of gamma emitting nuclides increases with an increase in the fuel burn-up and their removal ratios are found to be more than 99 wt.% except Co-60 and Cs-137....

The chlorination reaction kinetics of Zircaloy-4 cladding hulls were investigated using a home-made thermogravimetric analysis for a hull chlorination (TGA-HC) system. The reproducibility of the TGA-HC system was verified by repeated measurements at an identical condition, which showed only 6.6% of maximum difference. The effect of total flow rate...

The reaction between cesium iodide (CsI) and chlorine gas was quantitatively investigated using a thermo-gravimetric analysis system. A comparison between calculated and experimental results on the chlorine molar flow rate revealed that the reaction lies within the gas phase diffusion limited region under the condition of this work. Using the exper...

The pyroelectrochemical process has been widely used for the treatment of used nuclear fuel owing to its high proliferation resistance as well as a substantial reduction capability of high level nuclear wastes by recovering valuable materials such as uranium (U) and transuranic (TRU) elements. The pyroprocess developing at KAERI consists of a head-...

Surface oxidation behavior of ZIRLO (ZIRconium Low Oxidation) hulls was investigated using an X-ray photoelectron spectroscopy (XPS) technique. The effects of oxidation time (10-336 h at 500^{\circ}C) and temperature (400-700^{\circ}C for 10 h) were studied. Deconvolution results of the hulls oxidized at 500^{\circ}C revealed that a ZrO_2 phase app...

The pyroelectrochemical process has been widely used for the treatment of used nuclear fuel owing to its high proliferation resistance as well as a substantial reduction capability of high level nuclear wastes by recovering valuable materials such as uranium (U) and transuranic (TRU) elements. The pyroprocess developing at KAERI consists of a head-...

The effect of pretreatment processes for the Zr electrorefining of oxidized Zircaloy-4 cladding tubes is examined in LiCl–KCl–ZrCl4 molten salts at 500 °C. The cyclic voltammetries reveal that the Zr dissolution kinetics is highly dependent on the thickness of a Zr oxide layer formed at 500 °C under air atmosphere. For the Zircaloy-4 tube covered w...

Quaternary Pt2Ru1Fe1Ni1/C (M=Ni, Mo, or W) catalysts were investigated for the methanol electro-oxidation reaction (MOR). Electrocatalytic activities of the quaternary catalysts for CO electro-oxidation were studied via CO stripping experiments, and the Pt2Ru1Fe1Ni1/C and Pt2Ru1Fe1W1/C catalysts exhibited lowered on-set potential compared to that o...

The effect of fuel burn-up on the radioactivation behavior of cladding hull materials was investigated using the ORIGEN-S code for various materials of Zircaloy-4, Zirlo, HANA-4, and HANA-6 and for various fuel burn-ups of 30, 45, 60, and 75 GWD/MTU. The Zircaloy-4 material is the only one that does not contain Nb as an alloy constituent, and it wa...

Crystal structural analysis of Ho-doped ceria (Ce0.7Ho0.3O1.85) was performed using both conventional laboratory and synchrotron X-ray diffraction (XRD) data. In the laboratory XRD data, a poor refinement result was achieved based on a cubic phase (space group Fm-3 m, No.225); weighted (R wp) and profile (R p) R-factors were 16.2 and 13.4 %, respec...

Performance improvement of direct methanol fuel cells (DMFCs) was achieved via an anodic treatment technique. Previously, anodic treatment was performed using sulfuric acid as acidic media, but various organic acids including formic, acetic, oxalic, and citric acids were employed in this study to avoid the use of toxic sulfuric acid. By replacing s...

The recovery of Zr from Zircaloy-4 (Zry-4) cladding hulls was demonstrated to investigate the effect of the oxidation process on the reaction rate of the chlorination reaction. In chlorination reaction experiments performed for 6 h, where reaction products were collected every 2 h, it was observed that a significant decrease in the reaction rate wa...

The recovery of Zr from Zircaloy-4 (Zry-4) cladding hulls using a chlorination method was demonstrated for complete conversion of Zr into . A chlorination reaction was performed by reacting Zry-4 hulls for 8 h under a 70 cc/min + 70 cc/min Ar flow at . The initial weight of the reactant (51.7 g) decreased to 0.49 g after 8 h of operation, which is...

Zr electrorefining from Zircaloy-4 cladding hulls is demonstrated in LiCl-KCl-ZrCl4 molten salts at 500 degrees C. To examine the electrochemical behavior of Zr in molten salts, cyclic voltammetries and chronoamperometries are employed using a tungsten wire and Zr rod as a cathode and anode, respectively. Cyclic voltammetric measurement reveals mul...

Zr electrorefining for the treatment of Zircaloy-4 cladding hull waste is demonstrated in LiCl-KCl-ZrCl4 molten salts. Cyclic voltammetries using a W wire and a Zr rid as working and counter electrodes reveal that the Zr reduction process is an irreversible diffusion controlled mass transfer at 500°C. For a 10-g scale treatment, electrochemical dis...

The electrochemical behaviors of 10 g-scale fresh and oxidized Zircaloy-4 cladding hulls were examined in LiCl-KCl molten salts to confirm the feasibility of the electrorefining process for the treatment of hull wastes. In the results of measuring the potential-current response using a stainless steel basket filled with oxidized Zircaloy-4 hull spe...

The HSC chemistry code was employed to calculate the chemical and physical changes of Cs during the oxidative decladding and high temperature voloxidation processes. Five systems, Cs–O, Cs–I, Cs–Te, Cs–U, and Cs–Mo, were investigated to determine the stable phases at the oxidative decladding process, and to simulate a release of Cs from the stable...

Oxygen reduction reaction (ORR) is one of the most interesting research issues in the academia and industries due to its importance in polymer electrolyte membrane fuel cells. Development of new ORR catalysts with low cost and high activity is under intensive research, but it is a time-consuming process because of wide range of alloys to be explore...

The effect of the Zr oxide layer on the electrochemical dissolution of Zircaloy-4 cladding tubes is examined in LiCl-KCl-ZrCl4 molten salts at 500 degrees C. The cyclic voltammetry of Zircaloy-4 cladding tubes oxidized at 400 degrees C reveals an evident oxidation peak associated with an immediate dissolution of Zr, as also observed in the current...

The effect of oxidation conditions on the chlorination reaction behavior was investigated by using Zircaloy-4 (Zry-4) hulls oxidized at various conditions. When the hulls were oxidized at 500, 600, and 700 °C for 5 h, decrease of reactant mass after the chlorination reaction at 380 °C for 3 h was 41.6, 26.0, and 0.0 wt.%, respectively, while that o...

The effect of co-alloying of Co and Cr was investigated by synthesizing and analyzing Pt3M and PtM (M = Co and/or Cr) catalysts for the oxygen electro-reduction reaction (ORR) activity. In the Pt3M catalysts, we could not observe significant differences among the alloy catalysts before and after annealing, except for the high specific activity of a...

The present study a promising method for stabilizing spent filters trapping cesium and technetium by using magnesium phosphate ceramics. Simulated spent filters were fabricated by vaporizing nonradioactive cesium and rhenium (a surrogate of Tc) through the voloxidizer. In order to reveal the characteristics of spent filters, phase structures and th...

Chlorination reaction behavior of Zircaloy-4 hull waste was investigated by using HSC chemistry code as a function of decladding ratio. The Zircaloy-4 hull waste and residual spent nuclear fuel (SNF) remaining in the hull waste after oxidative decladding process were considered as reactants of the chlorination reaction. It was assumed that the hull...

Radioactivation of Zircaloy-4 (Zry-4) and Zirlo cladding hulls after 55 GWD/tU burn-up and 10 years of cooling was simulated using the ORIGEN-S code. The simulation results revealed that 125Sb and 60Co are major contributors of both radioactivity and decay heat in the case of the Zry-4 hulls. For the Zirlo hulls, 93mNb and 125Sb consisted 82.2% of...

Chlorination reaction behavior of Zircaloy-4 (Zry-4) cladding hulls was demonstrated by using a quartz reactor system. By reacting at 380 °C for 3 h, mass of the Zry-4 hulls decreased by 65.8 wt% with Cl2 utilization of 87.1 mol%. Composition of collected product was analyzed and it was revealed that concentration of Zr was higher than 99.97 wt%. T...

Chlorination reaction behavior of Zircaloy-4 (Zry-4) was simulated by using the HSC code for three different chlorinating reagents of Cl2, HCl, and CCl4. Four major components (Zr, Sn, Fe, and Cr) of Zry-4 and their oxides which were produced during an oxidative decladding process were considered for the theoretical calculation. The simulation resu...

Carbon supported Pt3Y (Pt3Y/C) and PtY (PtY/C) were investigated as oxygen reduction reaction (ORR) catalysts. After synthesis via reduction by NaBH4, the alloy catalysts exhibited 10–20% higher mass activity (mAmgPt−1) than comparably synthesized Pt/C catalyst. The specific activity (μAcmPt−2) was 23 and 65% higher for the Pt3Y/C and PtY/C catalys...

Both structural refinement using X-ray powder diffraction data and energy calculation using quantum mechanics were used to determine the site preference and the amount of Gd in the host lattice of Gd doped Fe3O4 [Gd(x)Fe(3-x)O4 (x = 0.1)] nanopowder prepared by the sonochemical method. Among possible cation-disorder models, the model proposed by st...

One of the major issues in direct methanol fuel cell research is to develop a new catalyst for methanol electro-oxidation reaction (MOR) with high activity and low cost. In this study, a new, simple, and economic way was introduced to improve the catalytic activity of commercial PtRu black catalyst for the MOR. A nanocomposite electrode was fabrica...

A combinatorial library of membrane-electrode-assemblies (MEAs) which consisted of 27 different compositions was fabricated to optimize the multilayer structure of direct methanol fuel cells. Each spot consisted of three layers of ink and a gradient was generated by employing different concentrations of the three components (Pt catalyst, Nafion® an...

A comparative study of carbon supported Pt30Co70, Pt30Cr70, and Pt30Co30Cr40 catalysts for oxygen electro-reduction reaction (ORR) activity was performed. In alloy catalysts synthesized via NaBH4 reduction, more than a 3-fold improvement was observed in ORR specific activity compared with that of Pt/C catalyst, while mass activities did not show si...

Carbon supported binary Pt–Ti alloys were investigated for application in methanol electro-oxidation (MOR) and oxygen electro-reduction reactions (ORR). Various compositions of Pt100−xTix/C (x=0, 25, 50, and 75) catalysts were synthesized by sequential impregnation of Pt and Ti followed by annealing at 900°C for 30min under H2/Ar flow. X-ray diffra...

A combinatorial library containing 645 different compositions was synthesised and characterised for methanol tolerant oxygen electro-reduction reaction (ORR) catalytic performance. The library was composed of compositions involving between 1 and 4 metals among Pt, Ru, Fe, Mo and Se. In an optical screening test, Pt(50)Ru(10)Fe(20)Se(10) composition...

Various compositions of binary and ternary Pt–Ni–Cr alloys were investigated as catalysts for the methanol electro-oxidation reaction (MOR). Among the binary (Pt28Ni72/C and Pt28Cr72/C) and ternary Pt–Ni–Cr catalysts (Pt28Ni36Cr36/C, Pt22Ni39Cr39/C, Pt33Ni31Cr36/C, and Pt33Ni36Cr31/C) examined, the Pt28Ni36Cr36/C composition exhibited the highest M...

The effect of heat treatment on a commercial PtRu/C catalyst was investigated with a focus on the relationship between electrochemical and surface properties. The heat treated PtRu/C catalysts were prepared by reducing the commercial PtRu/C catalyst at 300, 500, and 600 °C under hydrogen flow. The maximum mass activity for the methanol electro-oxid...

Ternary PtRuFe and PtRuMo alloy systems were investigated for methanol electro-oxidation reaction (MOR). Rapid optimization of the ternary alloy compositions was achieved via combinatorial synthesis and high-throughput screening method. A combinatorial library was composed of 121 different compositions of the ternary PtRuFe and PtRuMo alloys. High...

The ternary Pt–Co–Cr system was investigated for suitability as a methanol electro-oxidation reaction (MOR) catalyst by combinatorial synthesis and high-throughput screening method. A PtCoCr thin film library was prepared by a multi-target sputtering technique while parallel characterization was performed using a multichannel multielectrode analyze...

Ternary Pt45Ru45Mn10/C, Pt45Ru45Mo10/C and Pt45Ru45W10/C catalysts were synthesized and physical and electrochemical properties were characterized. Particle sizes of the catalysts were determined by X-ray diffraction to be 3.9, 4.8 and 4.6 nm for the Mn, Mo and W incorporated catalysts, respectively. Electrochemically active surface areas were calc...