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Current Status of Pyroprocessing Development at KAERI

Science and Technology of Nuclear Installations, 2013-01, Vol.2013 (2013), p.1-11

2013

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Electrorefining of Zirconium from Zircaloy-4 Cladding Hulls in LiCl-KCl Molten Salts

Journal of the Electrochemical Society, 2012-01, Vol.159 (8), p.D463-D468

2012

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A TGA study on the chlorination reaction kinetics of Zircaloy-4 cladding hulls

Journal of nuclear materials, 2015-04, Vol.459, p.175-182

2015

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Combinatorial search for oxygen reduction reaction electrocatalysts: A review

Journal of power sources, 2012-10, Vol.216, p.400-408

2012

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Quaternary Pt2Ru1Fe1M1/C (M=Ni, Mo, or W) catalysts for methanol electro-oxidation reaction

Korean Journal of Chemical Engineering, 2015, 32(2), 179, pp.206-215

2015

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Measurement of the thermal conductivity of TiO2 thin films by using the thermo-reflectance method

Thermochimica acta, 2007-04, Vol.455 (1-2), p.55-59

2007

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Preparation of uranium oxide powder for nuclear fuel pellet fabrication with uranium peroxide recovered from uranium oxide scraps by using a carbonate–hydrogen peroxide solution

Journal of radioanalytical and nuclear chemistry, 2012-05, Vol.292 (2), p.909-916

2012

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Effect of oxidation conditions on chlorination reaction of Zircaloy-4 hulls

Journal of nuclear materials, 2012-05, Vol.424 (1-3), p.153-157

2012

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PYROPROCESSING TECHNOLOGY DEVELOPMENT AT KAERI

Nuclear engineering and technology, 2011-08, Vol.43 (4), p.317-328

2011

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Irradiation tests and post-irradiation examinations of DUPIC fuel

Annals of nuclear energy, 2008-10, Vol.35 (10), p.1805-1812

2008

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Thermal expansion of UO2 and simulated DUPIC fuel

Journal of nuclear materials, 2002-03, Vol.301 (2-3), p.242-244

2002

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Characterization of irradiated simulated DUPIC fuel

Metals and materials international, 2001-10, Vol.7 (5), p.513-518

2001

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Stabilization of Cs/Re trapping filters using magnesium phosphate ceramics

Journal of radioanalytical and nuclear chemistry, 2013, Vol.295 (1), p.211-219

2013

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Uncertainty assessment for the thermal expansion of simulated fuel via the Monte Carlo method

Thermochimica acta, 2007-04, Vol.455 (1), p.114-118

2007

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Morphology study on the depleted uranium as hydriding/dehydriding cycles

Fusion engineering and design, 2016-11, Vol.109-111, p.146-151

2016

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Addition Effect of Fluoride Compounds for Zr Electrorefining in LiCl-KCl Molten Salts

International journal of electrochemical science, 2016, Vol.11 (1), p.566-576

2016

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The compressive creep behavior of (U, Ce)O2

Thermochimica acta, 2007-04, Vol.455 (1-2), p.109-113

2007

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Uncertainty evaluation of the thermal expansion of simulated fuel

Thermochimica acta, 2006-08, Vol.447 (2), p.197-201

2006

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Effect of Zr Oxide on the Electrochemical Dissolution of Zircaloy-4 Cladding Tubes

Journal of the Electrochemical Society, 2012-01, Vol.159 (11), p.E171-E176

2012

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Effects of pretreatment processes for Zr electrorefining of oxidized Zircaloy-4 cladding tubes

Journal of nuclear materials, 2014-06, Vol.449 (1-3), p.93-100

2014

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Chlorination reaction behavior of Zircaloy-4 hulls: experimental and theoretical approaches

Journal of radioanalytical and nuclear chemistry, 2012-05, Vol.292 (2), p.513-517

2012

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Chlorination reaction kinetics of CsI under cladding hull waste treatment condition: a TGA study

Journal of radioanalytical and nuclear chemistry, 2016-01, Vol.307 (1), p.333-339

2016

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Simulation of radioactivation and chlorination reaction behavior for Zircaloy-4 and Zirlo cladding hull wastes

Journal of radioanalytical and nuclear chemistry, 2012-06, Vol.292 (3), p.1221-1228

2012

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Effect of burn-up on the radioactivation behavior of cladding hull materials studied using the ORIGEN-S code

Journal of radioanalytical and nuclear chemistry, 2013-12, Vol.298 (3), p.1629-1633

2013

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Effect of chlorinating reagents on Zr recovery from Zircaloy-4 hull wastes: reaction behavior simulation by using the HSC code

Journal of radioanalytical and nuclear chemistry, 2012-04, Vol.292 (1), p.285-291

2012

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Current Status of Pyroprocessing Development at KAERI

Electrorefining of Zirconium from Zircaloy-4 Cladding Hulls in LiCl-KCl Molten Salts

A TGA study on the chlorination reaction kinetics of Zircaloy-4 cladding hulls

Combinatorial search for oxygen reduction reaction electrocatalysts: A review

Quaternary Pt2Ru1Fe1M1/C (M=Ni, Mo, or W) catalysts for methanol electro-oxidation reaction

Measurement of the thermal conductivity of TiO2 thin films by using the thermo-reflectance method

Preparation of uranium oxide powder for nuclear fuel pellet fabrication with uranium peroxide recovered from uranium oxide scraps by using a carbonate–hydrogen peroxide solution

Effect of oxidation conditions on chlorination reaction of Zircaloy-4 hulls

PYROPROCESSING TECHNOLOGY DEVELOPMENT AT KAERI

Irradiation tests and post-irradiation examinations of DUPIC fuel

Thermal expansion of UO2 and simulated DUPIC fuel

Characterization of irradiated simulated DUPIC fuel

Stabilization of Cs/Re trapping filters using magnesium phosphate ceramics

Uncertainty assessment for the thermal expansion of simulated fuel via the Monte Carlo method

Morphology study on the depleted uranium as hydriding/dehydriding cycles

Addition Effect of Fluoride Compounds for Zr Electrorefining in LiCl-KCl Molten Salts

The compressive creep behavior of (U, Ce)O2

Uncertainty evaluation of the thermal expansion of simulated fuel

Effect of Zr Oxide on the Electrochemical Dissolution of Zircaloy-4 Cladding Tubes

Effects of pretreatment processes for Zr electrorefining of oxidized Zircaloy-4 cladding tubes

Chlorination reaction behavior of Zircaloy-4 hulls: experimental and theoretical approaches

Chlorination reaction kinetics of CsI under cladding hull waste treatment condition: a TGA study

Simulation of radioactivation and chlorination reaction behavior for Zircaloy-4 and Zirlo cladding hull wastes

Effect of burn-up on the radioactivation behavior of cladding hull materials studied using the ORIGEN-S code

Effect of chlorinating reagents on Zr recovery from Zircaloy-4 hull wastes: reaction behavior simulation by using the HSC code

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