Jong-Bum Kim
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Research Subjects
Jong-Bum Kim has a total of 28 co-authors. Here are the top co-authors by number of shared publications:
Jae-Han Lee
6 shared publications- Hoe Woong Kim4 shared publications
Sung Kyun Kim
3 shared publicationsChang-Gyu Park
2 shared publications- Gyeong-Hoi Koo
Korea Atomic Energy Research Institute, Daejeon 34057, Korea
2 shared publications Hyeong-Yeon Lee
Fast Reactor Development Group, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu, Daejeon 305-353, Republic of Korea
2 shared publications
Latest Publications
- Open Access
- 1 June 2019
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 51 (3) , 922-929
Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance
- 1 June 2019
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 51 (3) , 922-929
Open AccessInfluence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance
- Open Access
- 1 June 2017
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 49 (4) , 855-864
Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor
- 1 June 2017
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 49 (4) , 855-864
Open AccessDrop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor
- Open Access
- 1 October 2016
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 48 (5) , 1083-1095
On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes
- 1 October 2016
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 48 (5) , 1083-1095
Open AccessOn the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes
- 30 June 2016
- Published by Korean Society of Pressure Vessels and Piping in Transactions of the Korean Society of Pressure Vessels and Piping
- Vol. 12 (1) , 134-140
Drop Performance Test of Control Rod Assembly for Prototype Gen-IV Sodium-cooled Fast Reactor
- 30 June 2016
- Published by Korean Society of Pressure Vessels and Piping in Transactions of the Korean Society of Pressure Vessels and Piping
- Vol. 12 (1) , 134-140
Drop Performance Test of Control Rod Assembly for Prototype Gen-IV Sodium-cooled Fast Reactor
- 30 June 2016
- Published by Korean Society of Pressure Vessels and Piping in Transactions of the Korean Society of Pressure Vessels and Piping
- Vol. 12 (1) , 93-100
Development of In-Service Inspection Techniques for PGSFR
- 30 June 2016
- Published by Korean Society of Pressure Vessels and Piping in Transactions of the Korean Society of Pressure Vessels and Piping
- Vol. 12 (1) , 93-100
Development of In-Service Inspection Techniques for PGSFR
- 20 January 2015
- Published by The Korean Society for Noise and Vibration Engineering in Transactions of the Korean Society for Noise and Vibration Engineering
- Vol. 25 (1) , 48-57
Development of a Ranging Inspection Technique in a Sodium-cooled Fast Reactor Using a Plate-type Ultrasonic Waveguide Sensor
- 20 January 2015
- Published by The Korean Society for Noise and Vibration Engineering in Transactions of the Korean Society for Noise and Vibration Engineering
- Vol. 25 (1) , 48-57
Development of a Ranging Inspection Technique in a Sodium-cooled Fast Reactor Using a Plate-type Ultrasonic Waveguide Sensor
- 1 September 2011
- Published by The Korean Society of Mechanical Engineers in Transactions of the Korean Society of Mechanical Engineers - A
- Vol. 35 (9) , 1083-1090
Concept Development and Review of Current Technical Issues for SFR Steam Generator
- 1 September 2011
- Published by The Korean Society of Mechanical Engineers in Transactions of the Korean Society of Mechanical Engineers - A
- Vol. 35 (9) , 1083-1090
Concept Development and Review of Current Technical Issues for SFR Steam Generator
- 1 August 2008
- Published by Elsevier in International Journal of Pressure Vessels and Piping
- Vol. 85 (8) , 550-556
Creep-fatigue test of a SA 316SS structure and comparative damage evaluations based upon elastic and inelastic approaches
- 1 August 2008
- Published by Elsevier in International Journal of Pressure Vessels and Piping
- Vol. 85 (8) , 550-556
Creep-fatigue test of a SA 316SS structure and comparative damage evaluations based upon elastic and inelastic approaches
- 1 January 2007
- Published by ASME International
- p. 307-314
Creep-Fatigue Damage and Crack Initiation for a Mod 9Cr-1Mo Structure With Weldments
A structural test and evaluation on creep-fatigue damage, and creep-fatigue crack initiation have been carried out for a Mod. 9Cr-1Mo steel structural specimen with weldments. The conservatisms of the design codes of ASME Section III subsection and NH and RCC-MR codes were quantified at the welded joints of Mod.9Cr-1Mo steel and 316L stainless steel with the observed images from the structural test. In creep damage evaluation using the RCC-MR code, isochronous curve has been used rather than directly using the creep law as the RCC-MR specifies. A y-shaped steel specimen of a diameter 500mm, height 440mm and thickness 6.35mm is subjected to creep-fatigue loads with two hours of a hold time at 600°C and a primary nominal stress of 30MPa. The defect assessment procedures of RCC-MR A16 guide do not provide a procedure for Mod.9Cr-1Mo steel yet. In this study application of σd method for the assessment of creep-fatigue crack initiation has been examined for a Mod. 9Cr-1Mo steel structure.
- 1 January 2007
- Published by ASME International
- p. 307-314
Creep-Fatigue Damage and Crack Initiation for a Mod 9Cr-1Mo Structure With Weldments
A structural test and evaluation on creep-fatigue damage, and creep-fatigue crack initiation have been carried out for a Mod. 9Cr-1Mo steel structural specimen with weldments. The conservatisms of the design codes of ASME Section III subsection and NH and RCC-MR codes were quantified at the welded joints of Mod.9Cr-1Mo steel and 316L stainless steel with the observed images from the structural test. In creep damage evaluation using the RCC-MR code, isochronous curve has been used rather than directly using the creep law as the RCC-MR specifies. A y-shaped steel specimen of a diameter 500mm, height 440mm and thickness 6.35mm is subjected to creep-fatigue loads with two hours of a hold time at 600°C and a primary nominal stress of 30MPa. The defect assessment procedures of RCC-MR A16 guide do not provide a procedure for Mod.9Cr-1Mo steel yet. In this study application of σd method for the assessment of creep-fatigue crack initiation has been examined for a Mod. 9Cr-1Mo steel structure.
- 1 November 2006
- Published by Elsevier in International Journal of Pressure Vessels and Piping
- Vol. 83 (11-12) , 826-834
Assessment of a creep-fatigue crack initiation and crack propagation for a welded cylindrical shell
- 1 November 2006
- Published by Elsevier in International Journal of Pressure Vessels and Piping
- Vol. 83 (11-12) , 826-834
Assessment of a creep-fatigue crack initiation and crack propagation for a welded cylindrical shell