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Thermal-Hydraulic Analysis for Conceptual Design of Korean HCCR TBM Set

IEEE transactions on plasma science, 2016-09, Vol.44 (9), p.1571-1575

2016

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Current Status of Korea Heat Load Test Facility KoHLT-EB for Fusion Reactor Materials

IEEE transactions on plasma science, 2017-07, Vol.45 (7), p.1820-1823

2017

Volltextzugriff (PDF)

Experimental study and discrete element method analysis of impact of vibration on pebble packing

Fusion engineering and design, 2024-01, Vol.198, p.114083, Article 114083

2024

Volltextzugriff (PDF)

Thermo-Mechanical Analysis for the Conceptual Design of Korean HCCR TBM-Set

IEEE transactions on plasma science, 2016-09, Vol.44 (9), p.1700-1703

2016

Volltextzugriff (PDF)

Study on hot isostatic pressing conditions of ARAA for fabrication of the breeding blanket first wall

Fusion engineering and design, 2024-05, Vol.202, p.114419, Article 114419

2024

Volltextzugriff (PDF)

Manufacturing and Examination for ITER Blanket First Wall Small-Scale Mockups With KoHLT-EB in Korea

IEEE transactions on plasma science, 2014-05, Vol.42 (5), p.1438-1442

2014

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Progress of Functional Components Design and Analysis of a Korean HCCR TBM in ITER

IEEE transactions on plasma science, 2014-05, Vol.42 (5), p.1443-1448

2014

Volltextzugriff (PDF)

Experimental validation of bed depth service time model using vapor adsorption bed for coolant purification system of fusion research

Fusion engineering and design, 2023-07, Vol.192, p.113716, Article 113716

2023

Volltextzugriff (PDF)

Development of fabrication technologies for the first wall of the HCCR blanket

Fusion engineering and design, 2022-11, Vol.184, p.113280, Article 113280

2022

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Mechanical Properties of Dissimilar TIG-Welded ARAA and SS316L Joint

IEEE transactions on plasma science, 2020-06, Vol.48 (6), p.1501-1504

2020

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Fabrication and testing of small mock-ups for helium cooled ceramic reflector breeding blanket development

Fusion engineering and design, 2021-06, Vol.167, p.112333, Article 112333

2021

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Contact Stress Evaluation Based on Thermal-Structural Analysis in KO HCCR TBM Submodules for ITER

IEEE transactions on plasma science, 2014-06, Vol.42 (6), p.1807-1810

2014

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Status of HCCR TBM program for DEMO blanket

Fusion engineering and design, 2021-10, Vol.171, p.112553, Article 112553

2021

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Vapor adsorption testing of ambient molecular sieve bed in coolant purification system

Fusion engineering and design, 2021-06, Vol.167, p.112371, Article 112371

2021

Volltextzugriff (PDF)

Preliminary Test and Evaluation of Nondestructive Examination for ITER First Wall Development in Korea

IEEE transactions on plasma science, 2012-09, Vol.40 (9), p.2285-2289

2012

Volltextzugriff (PDF)

Performance test and modeling with GAMMA-FR of helium circulator and recuperator for helium cooled breeding blanket

Fusion engineering and design, 2021-05, Vol.166, p.112299, Article 112299

2021

Volltextzugriff (PDF)

Design and experimental study of adsorption bed for the helium coolant purification system

Fusion engineering and design, 2020-06, Vol.155, p.111687, Article 111687

2020

Volltextzugriff (PDF)

High heat flux test with HIP-bonded Ferritic Martensitic Steel mock-up for the first wall of the KO HCML TBM

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.63-66

2011

Volltextzugriff (PDF)

Conceptual design and analysis of the HCCR breeder blanket for the K-DEMO

Fusion engineering and design, 2020-04, Vol.153, p.111513, Article 111513

2020

Volltextzugriff (PDF)

Plan and progress of the fusion neutron sources development at KAERI for fusion and fission applications

Fusion engineering and design, 2019-09, Vol.146, p.1419-1422

2019

Volltextzugriff (PDF)

Mechanical properties of ARAA steel after electron beam welding

Fusion engineering and design, 2017-11, Vol.124, p.774-778

2017

Volltextzugriff (PDF)

Long-Term Operation and Basic Corrosion Test in an Experimental Loop for Liquid Breeder in Korea

IEEE transactions on plasma science, 2012-03, Vol.40 (3), p.777-781

2012

Volltextzugriff (PDF)

Evaluation of ARAA steel E-beam welding characteristics for the fabrication of KO HCCR TBM

Fusion engineering and design, 2016-11, Vol.109-111, p.82-87

2016

Volltextzugriff (PDF)

Bonding techniques and performance qualification of plasma facing components for Korean fusion research

Fusion engineering and design, 2018-11, Vol.136, p.1510-1513

2018

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Corrosion Test Results of ARAA and FMS Steel in the Experimental Loop for Liquid Breeder

IEEE transactions on plasma science, 2018-07, Vol.46 (7), p.2663-2667

2018

Volltextzugriff (PDF)

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Thermal-Hydraulic Analysis for Conceptual Design of Korean HCCR TBM Set

Current Status of Korea Heat Load Test Facility KoHLT-EB for Fusion Reactor Materials

Experimental study and discrete element method analysis of impact of vibration on pebble packing

Thermo-Mechanical Analysis for the Conceptual Design of Korean HCCR TBM-Set

Study on hot isostatic pressing conditions of ARAA for fabrication of the breeding blanket first wall

Manufacturing and Examination for ITER Blanket First Wall Small-Scale Mockups With KoHLT-EB in Korea

Progress of Functional Components Design and Analysis of a Korean HCCR TBM in ITER

Experimental validation of bed depth service time model using vapor adsorption bed for coolant purification system of fusion research

Development of fabrication technologies for the first wall of the HCCR blanket

Mechanical Properties of Dissimilar TIG-Welded ARAA and SS316L Joint

Fabrication and testing of small mock-ups for helium cooled ceramic reflector breeding blanket development

Contact Stress Evaluation Based on Thermal-Structural Analysis in KO HCCR TBM Submodules for ITER

Status of HCCR TBM program for DEMO blanket

Vapor adsorption testing of ambient molecular sieve bed in coolant purification system

Preliminary Test and Evaluation of Nondestructive Examination for ITER First Wall Development in Korea

Performance test and modeling with GAMMA-FR of helium circulator and recuperator for helium cooled breeding blanket

Design and experimental study of adsorption bed for the helium coolant purification system

High heat flux test with HIP-bonded Ferritic Martensitic Steel mock-up for the first wall of the KO HCML TBM

Conceptual design and analysis of the HCCR breeder blanket for the K-DEMO

Plan and progress of the fusion neutron sources development at KAERI for fusion and fission applications

Mechanical properties of ARAA steel after electron beam welding

Long-Term Operation and Basic Corrosion Test in an Experimental Loop for Liquid Breeder in Korea

Evaluation of ARAA steel E-beam welding characteristics for the fabrication of KO HCCR TBM

Bonding techniques and performance qualification of plasma facing components for Korean fusion research

Corrosion Test Results of ARAA and FMS Steel in the Experimental Loop for Liquid Breeder

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