Soon-Heung Chang

发表

Uncertainty analysis of safety assessment for high-level radioactive waste repository

Won-Jin Cho, Soon-Heung Chang, Hun-Hwee Park, 1992 .

Axiomatic Design Approach for the advanced GT-MHR core

Soon-Heung Chang, Hd Jeong, 2008 .

Quantification of Overestimated Risk on Nuclear Power by Using Probabilistic Weighted Function

Soon-Heung Chang, Sub Lee Song, Soon-Heung Chang, 2011 .

PROBABILISTIC RISK ASSESSMENT OF NUCLEAR WASTE REPOSITORY WITH THE MECHANISTICALLY MODELED FAILURE RATE

Won-Jin Cho, Soon-Heung Chang, 1991 .

Integrated Assessment of National Power Sources Using AHP Technique

Sung-yeop Kim, Soon-Heung Chang, T. W. Kim, 2005 .

To Mars and Beyond with Nuclear Power - Design Concept of Korea Advanced Nuclear Thermal Engine Rocket

Seung Hyun Nam, Soon-Heung Chang, 2013 .

Intelligent Software System for the Advanced Control Room of a Nuclear Power Plant

Seong Soo Choi, Soon-Heung Chang, Gy Heo, 1997 .

A Study of the Predictive Model on the User Reaction Time using the Information Amount and Similarity

Soon-Heung Chang, Gy Heo, Sj Lee, 2004 .

Exploratory Study on Safety Objectives of the Fusion DEMO Plant

Soon-Heung Chang, Sang Ha An, Juhyung Lee, 2011 .

Stepwise Grouping Algorithm for Statistical Learning Framework

Soon-Heung Chang, Sang Ha An, 2009 .

Thermal Hydraulic Analysis of Thorium Fuel Assemblies Loaded with Annular Seed Pins

Soon-Heung Chang, Kh Han, 2002 .

Web-based Turbine Cycle Performance Analysis for Nuclear Power Plants

Seong Soo Choi, Soon-Heung Chang, Gy Heo, 2000 .

A Study on the Optimal Fuel Loading Pattern Design in Pressurized Water Reactor Using the Artificial Neural Network and Fuzzy Rule Based System

Byung Ho Lee, Soon-Heung Chang, Hyun-Koon Kim, 1993 .

Belief-Based Diagnosis Module for Turbine Cycles in NPPs

Soon-Heung Chang, Gy Heo, 2004 .

Development of the Distinctiveness Measure for a CRT based Information Display System using Excess Entropy Concept

Soon-Heung Chang, Jin Kyun Park, Sj Lee, 2000 .

CHF Enhancement in the Flow Boiling R-134a by Adding Wire Nets to Inner Surfaces of a Round Tube

Soon-Heung Chang, Sub Lee Song, Bs Shin, 2009 .

The Predictive Model on the User Reaction Time Using the Information Similarity

Soon-Heung Chang, Gy Heo, Sj Lee, 2005 .

Ubiquitous Computing for Complex Plant

Soon-Heung Chang, Sang Ha An, Won Joon Chang, 2006 .

Power Prediction in Nuclear Power Plants Using a Back-Propagation Learning Neural Network

Soon-Heung Chang, Myung-Sub Roh, Se-Woo Cheon, 1991 .

A dynamic reliability model for nuclear fuel element

Soon-Heung Chang, Kie-Yong Choi, Young-Ku Yoon, 1991 .

A probabilistic safety criterion for core melt frequency based on the distribution of the public's safety goals

Ki-Yong Ra, Byong-Whi Lee, Soon-Heung Chang, 1993 .

Passive Coping Strategy with Integrated Passive Safety System (IPSS) for Various LOCAS in SBO

Sang Ho Kim, Yong Hoon Jeong, Soon-Heung Chang, 2014 .

A STATISTICAL-MODEL FOR PREDICTION OF FUEL-ELEMENT FAILURE USING THE MARKOV PROCESS AND ENTROPY MINIMAX PRINCIPLES

Soon-Heung Chang, Kie-Yong Choi, Young-Ku Yoon, 1991 .

APPLICATION OF NEURAL NETWORKS TO CONNECTIONIST EXPERT SYSTEM FOR IDENTIFICATION OF TRANSIENTS IN NUCLEAR POWER PLANTS

Soon-Heung Chang, Se Woo Cheon, Gi Sik Kang, 1992 .

Research on Artificial Neural network Applications for Nuclear Power Plant

Soon-Heung Chang, Se-Woo Cheon, 1992 .

NEURAL NETWORK MODEL FOR ON-LINE THERMAL MARGIN ESTIMATION OF A NUCLEAR POWER PLANT

Soon-Heung Chang, Hyun-Koon Kim, Seung-Hyuk Lee, 1992 .

An Improved Cost-Benefit Criterion Using Utility Theory

Soon-Heung Chang, Ky Ra, 1984 .

Fourteen lessons learned from the successful nuclear power program of the Republic of Korea

Sungyeol Choi, Soon-Heung Chang, Eunju Jun, 2009 .

Algebraic Model for Root-Cause Diagnosis in Nuclear Turbine Cycles

Soon-Heung Chang, Gy Heo, 2004 .

Regulatory Framework for Controlling the Research Reactor Decommissioning Project

Soon-Heung Chang, 2009 .

Development of an uncertainty quantification method of the best estimate large LOCA analysis

Byung-Ho Lee, Soon-Heung Chang, Sang-Ryeol Park, 1992 .

Development of the on-line operator aid system (oasysm) using rule based expert system and fuzzy logic for nuclear power plants

Soon-Heung Chang, Sungyoung Choi, Kyu-Chang Kang, 1995 .

Integrated Passive Safety System (IPSS) for Ultimate Safe Nuclear Power Plants

Jae Young Choi, Soon-Heung Chang, Sang Ho Kim, 2012 .

Analysis for Design of Passive Safety Injection Line in IPSS

Soon-Heung Chang, Jihee Kim, Sang Ho Kim, 2013 .

On-line Monitoring Interface Development for Turbine Cycle Thermal Performance Test in Nuclear Power Plants

Soon-Heung Chang, Gy Heo, Sj Lee, 2000 .

Computerization of Performance Test Procedures in Gori NPP Unit 3&4

Soon-Heung Chang, Gy Heo, Sj Lee, 2003 .

Development of an expert system for performance evaluation and diagnosis in nuclear power plants

Soon-Heung Chang, Se-Woo Cheon, Ki-Sig-Kang, 1992, Conference Record for 1992 Fifth Conference on Human Factors and Power Plants.

Uncertainty and Sensitivity Analyses in Evaluating Risk of High Level Waste Repository

Byung Ho Lee, Soon-Heung Chang, T. W. Kim, 1988 .

Development of Performance Meassure for Advanced Alarm System Using Signal Detection Theory

Seong Soo Choi, Soon-Heung Chang, Jin Kyun Park, 1996 .

Development of an expert system for failure diagnosis of primary side systems

Soon-Heung Chang, Bok-Ki Min, Hak-Yeong Chung, 1992 .

Linear Programming Optimization of Nuclear fuel cycle in Korea

Soon-Heung Chang, Juno Lee, 2010 .

Thermal Performance Test through On-line Turbine Cycle Performance Monitoring in Nuclear Power Plants

Seong Soo Choi, Soon-Heung Chang, Gy Heo, 1999 .

Classification and Assessment of CHF Data in Round Tubes at Low Velocities

Soon-Heung Chang, 1994 .

CHF Experiments on the Reactor Vessel Wall using 2-D Slice Test Section

Won-Pil Baek, Yong Hoon Jeong, Soon-Heung Chang, 2003 .

Performance Test of the Quenching Meshes for Hydrogen Control

Soon-Heung Chang, Seong-Wan Hong, J. Song, 2003 .

Flow analyses using relap5/mod3 code for opr1000 under the external reactor vessel cooling

Kyoung-Ho Kang, Soon-Heung Chang, Rae-Joon Park, 2006 .

Experimental study on the heat transfer characteristics during the pressure transients under supercritical pressures

Kyoung-Ho Kang, Soon-Heung Chang, 2009 .

ICONE23-1124 INNOVATIVE NUCLEAR THERMAL ROCKET CONCEPT UTILIZING LEU FUEL FOR SPACE APPLICATION

Seung Hyun Nam, Jae Young Choi, Yong Hoon Jeong, 2015 .

Risk analysis of radioactive waste repository based on the time dependent hazard rate

Won-Jin Cho, Soon-Heung Chang, 1984 .

Critical heat flux of water in vertical round tubes at low pressure and low flow conditions

Soon-Heung Chang, Wp Baek, Soon-Heung Chang, 2000 .

The Applicability of a Quenching Mesh as a Hydrogen Flame Arrester in Nuclear Power Plants

Soon-Heung Chang, Seong-Wan Hong, J. Song, 2006 .

Neural network model for estimating departure from nucleate boiling performance of a pressurized water reactor core

Soon-Heung Chang, Hyun-Koon Kim, Seung-Hyuk Lee, 1993 .