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| 1 |
A Method of Tuning Optimization for PID Controller in Nuclear Power Plants
Sung, Chan Ho;Min, Moon Gi;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.1-6,
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| 2 |
Degradation Characteristics of Tubes in the Steam Generator Tubesheet
Cho, Nam Cheoul;Kang, Yong Suk;Kim, Heung Nam;Lee, Kuk-Hee;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.7-14,
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| 3 |
A Feasibility Test for Flaw Detection in Overlay Weld of Reactor Upper Head Penetration Using Time of Flight Diffraction Technique
Lee, Jeong Seok;Kim, Jin Hoi;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.15-19,
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| 4 |
Status of Inspection and Management for Nuclear Power Plants Snubbers
Cho, Yong-Bae;Moon, Gyoon-young;Yoo, Hyun-Joo;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.20-24,
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| 5 |
Effectiveness Verification of KHNP Safety Culture Principles and Assessment
Hur, Nam Young;Kim, Young Gab;Song, Tae-Young;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.25-30,
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| 6 |
Failure Mode Effective Analysis for selection of Single Point Vulnerability in New type Nuclear Power Plant
Hyun, Jin Woo;Yeam, Dong Un;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.31-36,
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| 7 |
A Study on the Work Management Method Considering Risks in Nuclear Power Plants
Song, Tae-Young;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.37-43,
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| 8 |
Development of Reactor Vessel Head Penetration Performance Demonstration System in Korea
Kim, Yongsik;Yoon, Byungsik;Yang, Seunghan;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.44-50,
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| 9 |
Probabilistic Safety Assessment of Nuclear Power Plants Using Alpha Factor Method for Common Cause Failure
Hwang, Seok-Won;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.51-55,
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| 10 |
Burst pressure tests of axial part-through-wall steam generator tubes
Lee, Kuk-Hee;Kim, Hong-Deok;Kang, Yong-Seok;Nam, Min-Woo;Cho, Nam-Cheoul;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.56-63,
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| 11 |
Improvement of Long-term Creep Life Prediction Method of Gr. 91 steel for VHTR Pressure Vessel
Park, Jae-Young;Kim, Woo-Gon;EKAPUTRA, I.M.W.;Kim, Seon-Jin;Kim, Min-Hwan;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.64-69,
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| 12 |
An Analysis of Operating Experience Reports on the Foreign JIT
Lee, Sang-Hoon;Kim, Jae-Hun;Song, Tae-Young;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.70-74,
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| 13 |
Simulation of Eddy Current Testing Signals Using Simulation Software Dedicated to Nondestructive Testing
Lee, Tae-Hun;Cho, Chan-Hee;Lee, Hee-Jong;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.75-81,
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| 14 |
A study on the change of microstructural and mechanical properties by the long-term thermal aging of dissimilar metal welds in nuclear power plants
Choi, Kyoung Joon;Yoo, Seung Chang;Kim, Ji Hyun;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.82-89,
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| 15 |
Nondestructive evaluation of wall thinning covered with insulation using pulsed eddy current
Park, Duck-Gun;Babu, M.K.;Lee, Duk-Hyun;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.90-95,
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| 16 |
Evaluation of Corrosion Product Behavior in NPP Secondary System with Complex Amine
JUNG, Hyunjun;RHEE, In Hyoung;Kim, Young In;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.96-99,
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| 17 |
High Strength SA508 Gr.4N Ni-Cr-Mo Low Alloy Steels for Larger Pressure Vessels of the Advanced Nuclear Power Plant
Kim, Min-Chul;Park, Sang-Gyu;Lee, Ki-Hyoung;Lee, Bong-Sang;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.100-106,
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| 18 |
Neutron Fluence Evaluation for Reactor Pressure Vessel Using 3D Discrete Ordinates Transport Code RAPTOR-M3G
Maeng, Young Jae;Lim, Mi Joung;Kim, Byoung Chul;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.107-112,
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| 19 |
Quantitative Estimation of Radiation Damage in Reactor Pressure Vessel Steels by Using Multiscale Modeling
Lee, Gyeong-Geun;Kwon, Junhyun;
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Korean Society of Pressure Vessels and Piping
, v.10, no.1, pp.113-121,
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