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Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Nuclear Engineering and Technology, 2016, 48(5), , pp.1059-1070

2016

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Preliminary study of fabrication technology for transmutation fuels using surrogate alloy

Journal of radioanalytical and nuclear chemistry, 2020-05, Vol.324 (2), p.451-457

2020

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Crystallographic characterization of irradiated U-10Zr and U-10Zr-5Ce metallic fuels

Journal of radioanalytical and nuclear chemistry, 2017-12, Vol.314 (3), p.2579-2583

2017

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Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Metals (Basel ), 2016-11, Vol.6 (11), p.278-278

2016

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Mechanical design of a sodium cooled fast reactor fuel assembly in Korea: Normal operation condition

Nuclear engineering and design, 2019-05, Vol.346, p.67-74

2019

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Thermo-mechanical behavior of all the metallic fuel rods in a sodium-cooled fast reactor

Nuclear engineering and design, 2018-12, Vol.339, p.126-136

2018

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Sodium fast reactor evaluation: Core materials

Journal of nuclear materials, 2009-07, Vol.392 (2), p.324-330

2009

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Radiochemical behavior of nitrogen species in high temperature water

Nuclear Engineering and Technology, 2023, 55(9), , pp.3183-3193

2023

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Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

Nuclear Engineering and Technology, 2016, 48(5), , pp.1096-1108

2016

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Pore pressure and swelling in the rim region of LWR high burnup UO2 fuel

Journal of nuclear materials, 2001-06, Vol.295 (2-3), p.213-220

2001

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Measurement of microstructure and eutectic penetration rate on irradiated metallic fuel after high-temperature heating test

Metals and Materials International, 2017, 23(3), , pp.504-511

2017

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Small punch test for determining a flow stress by using a hybrid inverse procedure

Computational materials science, 2008-10, Vol.43 (4), p.744-751

2008

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The effect of RE-rich phase on the thermal conductivity of U–Zr–RE alloys

Journal of nuclear materials, 2009-04, Vol.385 (3), p.559-562

2009

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Molecular dynamics simulation of the pressure–volume–temperature data of xenon for a nuclear fuel

Journal of nuclear materials, 2008-01, Vol.372 (1), p.89-93

2008

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Radiochemical behavior of nitrogen species in high temperature water

Nuclear engineering and technology, 2023, Vol.55 (9), p.3183-3193

2023

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An extension of the two-zone method for evaluating a fission gas release under an irradiation-induced resolution flux

Journal of nuclear materials, 2008-02, Vol.373 (1), p.280-288

2008

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Evaluation of thermal aging embrittlement in CF8 duplex stainless steel by small punch test

Journal of nuclear materials, 2000, Vol.278 (1), p.96-103

2000

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Measurement of the specific heat of Zr–40 wt%U metallic fuel

Journal of nuclear materials, 2007-03, Vol.360 (3), p.315-320

2007

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A two-zone method with an enhanced accuracy for a numerical solution of the diffusion equation

Journal of nuclear materials, 2006-12, Vol.359 (1), p.139-149

2006

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Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO2 Fuels

Nuclear technology, 2007-01, Vol.157 (1), p.53-64

2007

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Interaction behavior between binary xCe-yNd alloy and HT9

Journal of nuclear materials, 2016-10, Vol.479, p.394-401

2016

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Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

Nuclear engineering and technology, 2016, Vol.48 (5), p.1096-1108

2016

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Evaluation of a pellet-clad mechanical interaction in mixed oxide fuels during power transients by using axisymmetric finite element modeling

Nuclear engineering and design, 2004-06, Vol.231 (1), p.39-50

2004

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Electro-acupuncture reverses nerve growth factor abundance in experimental polycystic ovaries in the rat

Gynecologic and obstetric investigation, 2004-01, Vol.57 (2), p.80-85

2004

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Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Nuclear engineering and technology, 2016, Vol.48 (5), p.1059-1070

2016

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Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Preliminary study of fabrication technology for transmutation fuels using surrogate alloy

Crystallographic characterization of irradiated U-10Zr and U-10Zr-5Ce metallic fuels

Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Mechanical design of a sodium cooled fast reactor fuel assembly in Korea: Normal operation condition

Thermo-mechanical behavior of all the metallic fuel rods in a sodium-cooled fast reactor

Sodium fast reactor evaluation: Core materials

Radiochemical behavior of nitrogen species in high temperature water

Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

Pore pressure and swelling in the rim region of LWR high burnup UO2 fuel

Measurement of microstructure and eutectic penetration rate on irradiated metallic fuel after high-temperature heating test

Small punch test for determining a flow stress by using a hybrid inverse procedure

The effect of RE-rich phase on the thermal conductivity of U–Zr–RE alloys

Molecular dynamics simulation of the pressure–volume–temperature data of xenon for a nuclear fuel

Radiochemical behavior of nitrogen species in high temperature water

An extension of the two-zone method for evaluating a fission gas release under an irradiation-induced resolution flux

Evaluation of thermal aging embrittlement in CF8 duplex stainless steel by small punch test

Measurement of the specific heat of Zr–40 wt%U metallic fuel

A two-zone method with an enhanced accuracy for a numerical solution of the diffusion equation

Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO2 Fuels

Interaction behavior between binary xCe-yNd alloy and HT9

Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

Evaluation of a pellet-clad mechanical interaction in mixed oxide fuels during power transients by using axisymmetric finite element modeling

Electro-acupuncture reverses nerve growth factor abundance in experimental polycystic ovaries in the rat

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

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