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1
A Safety Assessment Methodology for a Digital Reactor Protection System
A Safety Assessment Methodology for a Digital Reactor Protection System
Dong-Young Lee, | 제어자동화시스템공학회 | 2006 ,
2
High Temperature Structural Integrity Evaluation Method and Application Studies by ASME-NH for the Next Generation Reactor Design
High Temperature Structural Integrity Evaluation Method and Application Studies by ASME-NH for the Next Generation Reactor Design
Gyeong-Hoi koo., | 대한기계학회 | 2006 ,
3
Fault Detection, Monitoring and Diagnosis of Sequencing Batch Reactor for Integrated Wastewater Treatment
Fault Detection, Monitoring and Diagnosis of Sequencing Batch Reactor for Integrated Wastewater Treatment
Chang Kyoo Yoo, | 대한환경공학회 | 2006 ,
4
Diesel Engine NOx Reduction By SNCR Under Simulated Flow Reactor Conditions
Diesel Engine NOx Reduction By SNCR Under Simulated Flow Reactor Conditions
Chang Mo Nam, | 대한환경공학회 | 2006 ,
5
Effects of Thermal Contact Resistance on Film Growth Rate in a Horizontal MOCVD Reactor
Effects of Thermal Contact Resistance on Film Growth Rate in a Horizontal MOCVD Reactor
Ik-Tae Im, Nag Jung Choi, Masakazu Sugiyame, Yosh, | 대한기계학회 | 2005 ,
6
Fluid Effects on the Core Seismic Behavior of a Liquid Metal Reactor
Fluid Effects on the Core Seismic Behavior of a Liquid Metal Reactor
Gyeong-Hoi Koo, Jae-Han Lee, | 대한기계학회 | 2004 ,
7
Design of a Nuclear Reactor Controller Using a Model Predictive Control Method
Design of a Nuclear Reactor Controller Using a Model Predictive Control Method
Man Gyun Na, Dong Won Jung, Sun Ho Shin, Sun Mi L, | 대한기계학회 | 2004 ,
8
Structural Integrity Evaluation for Interference-fit Flywheels in Reactor Coolant Pumps of Nuclear Power Plants
Structural Integrity Evaluation for Interference-fit Flywheels in Reactor Coolant Pumps of Nuclear Power Plants
June-Soo Park, Ha-Cheol Song, Ki-Seok Yoon, Taek-, | 대한기계학회 | 2005 ,
9
Numerical Study on the Low Density Gas Flows in a Plasma Etch Reactor
Numerical Study on the Low Density Gas Flows in a Plasma Etch Reactor
Joong-Sik Heo, Young-Kyu Hwang, | 대한기계학회 | 2005 ,
10
KSNP+ Reactor Vesel Head Drop Analysis for a 5.5M Free Fall
KSNP+ Reactor Vesel Head Drop Analysis for a 5.5M Free Fall
Ihn Namgung, Seung Ha, Jeong, Dae Hee Lee, Taek S, | 대한기계학회 | 2005 ,
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