Welcome

The major improvements in the quality of human life were achieved by using extra source of energy such as coal, oil, gas, and nuclear. Before humankind moves to the Fusion energy era, nuclear fission energy will play a critical role for energy supply. We are aiming at assuring the intrinsic safety of nuclear fission power, so that its merits such as no greenhouse gas emission and reliable supply at low cost can contribute the sustainable growth of society.

Nuclear Plant Reliability and

Information Lab

The history of Rensselaer Polytechnic Institute (RPI) spans nearly two hundred years beginning with its founding in 1824. Rensselaer launched its plan for NE research in the late 1950s. Our lab is nesting at Rensselaer since 2016. Yes, we are working to develop an inherently safe nuclear power based on the researches on risk assessment and new intelligence. Our research covers Passive safety system design and operation, Dynamic risk assessment, Digitalized plant risk quantification, Cyber security, Software reliability estimation, Emergency operation procedure, and Human operators behavior.

Hyun Gook Kang

Students

Inseop Jeon

• Research interests: Passive safety system operation • Course: Ph.D. candidate • Email: jeoni(at)rpi.edu • MS (2015) nuclear engineering from KAIST • BS (2013) nuclear engineering from Kyunghee Univ.

Asad Ullah Amin Shah

• Research interests: Dynamic probabilistic risk assessment • Course: Ph.D. candidate • Email: shaha11(at)rpi.edu • MS (2015) nuclear engineering from KAIST

Junyung Kim

• Research interests: Data analytic • Course: Ph.D. candidate • Email: kimj42(at)rpi.edu • BS (2012) applied statistics from Yonsei Univ.

Sang Hun Lee

• Research interests: Digitalized plant risk • Course: Ph.D. candidate • Email: lees35(at)rpi.edu • MS (2016) nuclear engineering from KAIST • BS (2014) nuclear engineering from KAIST

Researcher

Post Doctoral Researcher

• coming soon

Alumni

Dr. Sung Min Shin

• Korea Atomic Energy Research Institute • Email: smshin(at)kaeri.re.kr • Ph.D. from KAIST (2015)

Mirae Yoon

• Korea Atomic Energy Research Institute • Email: future(at)kaeri.re.kr • MS from KAIST (2016)

Dr. Bo Gyung Kim

• Korean Institute of Nuclear Safety • Email: bogyungkim(at)kins.re.kr • Ph.D. from KAIST (2016)

Kyung Min Yoon

• KEPCO Nuclear Fuel Co., Ltd. • Email: kmyoon7(at)kaist.ac.kr • MS from KAIST (2016)

Inhyo Lee

• Email: lih9103(at)kaist.ac.kr • MS from KAIST (2016)

Dr. Kwang Seop Son

• Korea Atomic Energy Research Institute • Email: ksson78(at)kaeri.re.kr • Ph.D. from KAIST (2017)

Dr. Hee Eun Kim

• Korean Atomic Energy Research Institute • Email: heeeunkim(at)kaeri.re.kr • Ph.D. from KAIST (2018)

Dr. Robby Christian

•   • Email: chrisr3(at)rpi.edu • Ph.D. from RPI (2019)

Dr. Jaehyun Ham

•   • Email: turbulent(at)kaist.ac.kr • Ph.D. from KAIST (2019)

Dr. Sanghee Kang

• Korea Hydro & Nuclear Power • Email: sanghee.kang(at)khnp.co.kr • Ph.D. from KAIST (2019)

Research

 

Dynamic Risk Assessment

While a classic static risk assessment addresses the time-averaged response of the plant, recently developed dynamic risk assessment for capturing time-line uncertainty of complex plant behavior under various accident conditions. In nuclear plants, when any deviation is detected, a plant protection system will generate safety signals for the reactor trip and the engineered safety feature actuation. After that, human operators will perform the actions specified in the emergency operation procedure. This process has its own uncertainty and of course dynamics of plant response will be mixed into this pile of uncertainties. Not only in nuclear plants, in other time-dependent events such as transportation, understanding their dynamics is the most important task for risk assessment. Static event trees in the conventional PRAs, however, have limited capability to capture all this varieties.          

 

Passive Safety System Operation

Emergency operating guidelines (EOG) provide technical guidance for  plant specific emergency operating procedures. These guidelines provide the actions necessary for mitigation of plant deviation . Since passive safety features are added to conventional active safety systems, the development of EOG which fits to both of safety system is big issue. The plant safety will be drastically enhanced by having suitable EOG.

 

Digitalized Plant Risk Assessment

There are many reliability and risk issues in safety-critical digital control systems. By identifying and analyzing those issues, we can suggest countermeasures and eliminate potential risk factors. Quantification of software reliability is one of the most important issues. Most digital systems are adopting software to make the system behave as designed, thus the reliability of the system is directly related to the software faults. The method of quantification of software reliability may include software testing. However, the behavior and the reliability criteria of the software used in the NPP are different from other software, so the test case generation method should be newly developed. One more challenging issue is the assessment of risk caused by safety network communication for which we are developing a new quantification method.

Check the updated list at Google Scholar

Journal Papers

1. Man Cheol Kim, Jungil Seo, Wondea Jung, Jong Gyun Choi, Hyun Gook Kang, Seung Jun Lee, “Evaluation of Effectiveness of Fault-Tolerant Techniques in a Digital Instrumentation and Control System with a Fault Injection Experiment,” Nuclear Engineering and Technology, In press, 2018. 2. Sanghee KangA, Sun Heo, Hyun Gook Kang, “Performance analysis of the passive safety features of iPOWER under Fukushima-like accident conditions,” Nuclear Engineering and Technology, In press, 2018. 3. Jae Hyun Ham, Hyun Gook Kang, “RCD success criteria estimation based on allowable coping time,” Nuclear Engineering and Technology, Accepted for publication, 2018. 4. Seung Jun Lee, Sang Hun Lee, Tsong-Lun Chu, Athi Varuttamaseni, Meng Yue, Ming Li, Heung Seop Eom, and Hyun Gook Kang, “Bayesian Belief Network Model Quantification using Distribution-based Node Probability and Experienced Data Updates for Software Reliability Assessment,” IEEE Access, Vol.6, pp. 64556-64568, 2018. 5. Hyun Gook Kang, Sang Hun Lee, Seung Jun Lee, Tsong-Lun Chu, Athi Varuttamaseni, Meng Yue, Steve Yang, Heung Seop Eom, and Ming Li, “Development of a Bayesian Belief Network Model for Software Reliability Quantification of Digital Protection Systems in Nuclear Power Plants,” Annals of Nuclear Energy, Vol. 120, Pages 62-73, 2018. 6. Kyung-min Yoon and Hyun Gook Kang, “A Case Study of Time-dependent Risk informed Integrated Safety Assessment under Complex Accident Sequences,” Nuclear Engineering and Design, Vol. 333, Pages 63-75, 2018. 7. Sang Hun Lee, Seung Jun Lee, Jinkyun Park, Eun-chan Lee, Hyun Gook Kang, “Development of Simulation-based Testing Environment for Safety-critical Software,” Nuclear Engineering and Technology, Vol. 50, No. 4, 2018. 8. In Seop Jeon, Sang Hee Kang, Ho Lim Moon, and Hyun Gook Kang, “Risk effect of the Hybrid-SIT system under SGTR accidents,” Nuclear Engineering and Design, Vol. 326, 2018. 9. Hee Eun Kim, Han Seong Son, Jaehyun Cho, Sung Shin, and Hyun Gook Kang, “Input-domain Software Testing for Failure Probability Estimation of Safety-critical Applications in Consideration of Past Input Sequence,” IEEE Access, Vol. 6, pp. 8440-8451, 2018. 10. Sung Min Shin, Dong San Kim, Hyun Gook Kang, “Power-operated check valve in abnormal situations,” Nuclear Engineering and Design, Vol. 330, 2018 11. Kwang Seop Son, Dong Hoon Kim, Gee Yong Park, Hyun Gook Kang, “Availability analysis of safety grade multiple redundant controller used in advanced nuclear safety systems,” Annals of Nuclear Energy, Vol.111, Pages 73-81, 2018. 12. Sang Hun Lee, Kwang Seop Son, Wondea Jung, Hyun Gook Kang, “Risk assessment of safety data link and network communication in digital safety feature control system of nuclear power plant,” Annals of Nuclear Energy, Volume 108, Pages 394-405, 2017. 13. Hee Eun Kim, Han Seong Son, Jonghyun Kim, and Hyun Gook Kang, “Systematic development of scenarios caused by cyber-attack-induced human errors in nuclear power plants,” Reliability Engineering and System Safety, Vol. 167, Pages 290-301, 2017. 14. In Seop Jeon, Hyun Gook Kang, “Development of a Feed-and-Bleed Operation Strategy with Hybrid-SIT under Low Pressure Condition of PWR,” Nuclear Engineering and Design, Vol. 314, Pages 150-164, 2017. 15. Mirae Yun, Robby Christian, Bo Gyung Kim, Belal Almomani, Jaehyun Ham, Sanghoon Lee and Hyun Gook Kang, “A software tool for the integrated risk assessment of spent fuel transportation and storage,” Nuclear Engineering and Technology, Vol. 49, Pages 721-733, 2017. 16. Belal Almomani, Sanghoon Lee, Dongchan Jang, Hyun Gook Kang, “Development of a Probabilistic Safety Assessment Framework for an Interim Dry Storage Facility Subjected to an Aircraft Crash Using Best-Estimate Structural Analysis,” Nuclear Engineering and Technology, Vol. 49, Pages 411-425, 2017. 17. Belal Almomani, Sanghoon Lee, Dongchan Jang, Hyun Gook Kang, “Probabilistic Risk Assessment of Aircraft Impact on a Spent Nuclear Fuel Dry Storage,” Nuclear Engineering and Design, Vol. 311, Pages 104-119, 2017. 18. Robby Christian, Hyun Gook Kang, “Probabilistic Risk Assessment on Maritime Spent Nuclear Fuel Transportation (Part II: Ship Collision Probability),” Reliability Engineering and System Safety, Vol. 164, 136-149, 2017. 19. Robby Christian, Hyun Gook Kang, “Probabilistic Risk Assessment on Maritime Spent Nuclear Fuel Transportation (Part I: Transport Cask Damage Probability),” Reliability Engineering and System Safety, Vol. 164, 124-135, 2017. 20. Mirae Yun, Robby Christian, Belal Almomani, and Hyun Gook Kang, “Insights from risk analysis of spent fuel transportation and interim storage,” International Journal of Nuclear Safety and Simulation, Vol.7, No.2, 2016. 21. Bo Gyung Kim, Ho Joon Yoon, Hyun Gook Kang “Development of a Systematic Sequence Tree Model for Feed-and-Bleed Operation under a Combined Accident,” Annals of Nuclear Energy, Vol.98, Pages 200-210, 2016. 22. Belal Almomani, Sanghoon Lee, Hyun Gook Kanga, " Structural Analysis of a Metal Spent-Fuel Storage Cask in an Aircraft Crash for Risk Assessment," Nuclear Engineering and Design, Vol.308, Pages 60-72, 2016. 23. Bohwan Choi, Gi Chan Jang; Sung Min Shin; Soo Ill Lee; Hyun Gook Kang, Chun Taek Rim, “Development of Highly Reliable Power and Communication System for Essential Instruments under Severe Accidents in NPP,” Nuclear Engineering and Technology, In press, online available, 2016. 24. Hyun Gook Kang, Sungmin Shin, “Overview of risk assessment in digitalized nuclear power plants,” International Journal of Nuclear Safety and Simulation, Vol. 7, No.1, 2016. 25. Mirae Yun, Sang Hun Lee, and Hyun Gook Kang, “Analysis of the Relationship between Risk Perception and Willingness to Pay for Nuclear Power Plant Risk Reduction,” Science and Technology of Nuclear Installations, Volume 2016. 26. Sang Hun Lee, Hyun Gook Kang, “Integrated Framework for the External Cost Assessment of Nuclear Power Plant Accident considering Risk Aversion,” Energy Policy, Volume 92, May 2016. 27. Sung Min Shin, Bo Hwan Choi, Hyun Gook Kang, “Motor Health Monitoring at Standstill through Impedance Analysis,” IEEE Transactions on Industrial Electronics Technology, Volume 63, Issue 7, 2016. 28. Kwang Seop Son, Chang Hwoi Kim, Hyun Gook Kang, "Study on the systematic approach of Markov modeling for dependability analysis of complex fault-tolerant features with voting logics," Reliability Engineering and System Safety, Vol. 150, 2016. 29. Seung Woo Lee, Ar Ryum Kim, Jinkyun Park, Hyun Gook Kang, Poong Hyun Seong, “Measuring Situation Awareness of Operating Team in Different Main Control Room Environments of Nuclear Power Plants,” Nuclear Engineering and Technology, Vol. 48(1), 2016. 30. In Seop Jeon, Hyun Gook Kang, “Optimal Operation of Hybrid-SITs under a SBO accident,” Nuclear Engineering and Design, Vol. 297, 2016. 31. Bo Gyung Kim, Ho Joon Yoon, Jaewhan Kim, Hyun Gook Kang “Advanced Operation Strategy for Feed-and-Bleed Operation in an OPR1000,” Annals of Nuclear Energy, Vol. 90, 2016. 32. Hyun Gook Kang, Bo Gyung Kim, “Review of Korean activities on PSA and its application for NPP,” International Journal of Nuclear Safety and Simulation, Vol. 6, 2015. 33. Gyunyoung Heo, Poong Hyun Seong and Hyun Gook Kang, “Emerging I&C technologies under the shifting regulatory environment in South Korea,” Frontiers in Energy Research, April 2015. 34. Sang Hun Lee, Hee Eun Kim, Kwang Seop Son, Sung Min Shin, Seung Jun Lee, Hyun Gook Kang, “Reliability Modeling of Safety-Critical Network Communication in a Digitalized Nuclear Power Plant,” Reliability Engineering and System Safety, Vol. 144, 2015. 35. Robby Christian, Seon Ho Song, Hyun Gook Kang, “Study of Core Support Barrel Vibration Monitoring Using Ex-Core Neutron Noise Analysis and Fuzzy Logic Algorithm”, Nuclear Engineering and Technology, Vol. 47(2), 2015. 36. Sang Hun Lee, Hyun Gook Kang, “Integrated Societal Risk Assessment Framework for Nuclear Power and Renewable Energy Sources”, Nuclear Engineering and Technology, Vol. 47(4), 2015. 37. Sung Min Shin, In Seop Jeon, Hyun Gook Kang, “Surveillance test and monitoring strategy for the availability improvement of standby equipment using age-dependent model”, Reliability Engineering and System Safety, Vol. 135, 2015. 38. In Seop Jeon, Hyun Gook Kang, “Development of Operation Strategy for Hybrid-SIT with Active System”, Nuclear Engineering and Technology, Vol. 47(4), 2015. 39. Kwang Seop Son, Chang Hwoi Kim, Hyun Gook Kang, “Conceptual design of emergency communication system to cope with severe accidents in NPPs and its performance evaluation”, Annals of Nuclear Energy, Vol.76, Pages 367-377, 2015. 40. Min Yoo, Sung Min Shin, and Hyun Gook Kang, “Development of Instrument Transmitter Protecting Device against High-Temperature Condition during Severe Accidents”, Science and Technology of Nuclear Installations, Volume 2014. 41. Bo Gyung Kim, Hyun Gook Kang, Ho Joon Yoon, Sang Ho Kim, “Dynamic sequence analysis for feed-and-bleed operation in an OPR1000”, Annals of Nuclear Energy, Vol. 71, Pages 361-375, 2014. 42. Bo Gyung Kim, Hyun Gook Kang, Hee Eun Kim, Seung Jun Lee, Poong Hyun Seong, “Reliability modeling of digital component in plant protection system with various fault-tolerant techniques”, Nuclear Engineering and Design, Volume 265, Pages 1005–1015, 2013. 43. Sung Min Shin, Bo Gyung Kim, Hyun Gook Kang, "Monitoring Method Development for Safety Component on Standby State", Chemical Engineering Transactions, Vol . 33, 2013. 44. Poong Hyun Seong, Hyun Gook Kang, Man Gyun Na, Jong Hyun Kim, Gyunyoung Heo And Yoensub Jung, “Advanced MMIS Toward Substantial Reduction In Human Errors In NPPs”, Nuclear Engineering and Technology, Vol. 45, No. 2, 2013. 45. Ar Ryum Kim, Seung Woo Lee, Jin Kyun Park, Hyun Gook Kang, and Poong Hyun Seong, “Correlation Analysis between Team Communication Characteristics and Frequency of Inappropriate Communications,” Annals of Nuclear Energy, Vol. 58, 2013. 46. Ahmed Saeed Al Shehhi, Soon Heung Chang, Sang Ho Kim and Hyun Gook Kang, “Analysis of economics and safety to cope with station blackout in PWR”, Annals of Nuclear Energy, Vol. 59, 2013. 47. Inseok Jang, Ar Ryum Kim, Mohamed Ali Salem Al Harbi, Seung Jun Lee, Hyun Gook Kang, Poong Hyun Seong, “An empirical study on the basic human error probabilities for NPP advanced main control room operation using soft control”, Nuclear Engineering and Design, Volume 257, April 2013. 48. Mohamed Ali Salem Al Harbi, Ar Ryum Kima, Inseok Jang, Poong Hyun Seong, Shigenori Shirouzu, Sotetsu Katayama, Hyun Gook Kang, “Effects of Soft Control in the Nuclear Power Plants Emergency Operation Condition”, Annals of Nuclear Energy, Volume 54, April 2013. 49. Gee-Yong Park, Heung-Seop Eom, Seung Cheol Jang, and Hyun Gook Kang, “Software Failure Probability Assessment by Bayesian Inference”, Nuclear Technology, Vol. 183, No.1, 2013. 50. Heung-seop Eom, Gee-yong Park, Seung-cheol Jang, Han Seong Son, and Hyun Gook Kang, “V&V-based Remaining Fault Estimation Model for Safety-Critical Software of a Nuclear Power Plant”, Annals of Nuclear Energy, Vol. 51, Page 38–49, 2013. 51. Ar Ryum Kim, Jin Kyun Park, Seung Woo Lee, In Seok Jang, Hyun Gook Kang, and Poong Hyun Seong, “Development of New Taxonomy of Inappropriate Communication and its Application to Operating Teams in Nuclear Power Plants”, Nuclear Engineering and Technology, Vol. 44, No. 8, 2012. 52. Shingenori Shirouzu, Sotetsu Katayama, Ar Ryum Kim, Inseok Jang, Mohamed Ali Salem Al Harbi, Poong Hyun Seong, Hyun Gook Kang, “Effect of Education on Subjects’ Physiological Measurements”, Human Development for ALL, Vol.2 No.1, 2012 53. Hyun Gook Kang and Hee Eun Kim, "Unavailability and Spurious Operation Probability of k-out-of-n Reactor Protection Systems in Consideration of CCF", Annals of Nuclear Energy, Volume 49, November 2012, Pages 102–108. 54. Jong Gyun Choi, Seung Jun Lee, Hyun Gook Kang, Seop Hur, Young Jun Lee, and Seung Cheol Jang, “Fault Detection Coverage Quantification of Automatic Test Functions of Digital I&C System in NPPs”, Nuclear Engineering and Technology, Vol. 44, No. 4, Page 421 (8 Pgs.), 2012. 55. Mohammad Khalaquzzaman, Hyun Gook Kang, Man Cheol Kim, and Poong H. Seong, “Optimization of periodic testing frequency of a reactor protection system based on a risk-cost model and public risk perception”, Nuclear Engineering and Design, Vol. 241, No. 5, 2011. 56. Seung Jun Lee, Jong Gyun Choi, Hyun Gook Kang, and Seung-Cheol Jang, "Reliability Assessment Method for NPP Digital I&C Systems considering the Effect of Automatic Periodic Tests", Annals of Nuclear Energy, Vol. 37, No. 11, 2010. 57. Mohammad Khalaquzzaman, Hyun Gook Kang, Man Cheol Kim, and Poong H. Seong, “A model for estimation of reactor spurious shutdown rate considering maintenance human errors in reactor protection system of nuclear power plants”, Nuclear Engineering and Design, Vol. 240, No. 10, 2010. 58. Mohammad Khalaquzzaman, Hyun Gook Kang, Man Cheol Kim, Seung Cheol Jang and Poong H. Seong, “Quantification of Unavailability Caused by Random Failures and Maintenance Human Errors”, Nuclear Engineering and Design, Vol. 140, No. 6, 2010. 59. Han Seong Son, Hyun Gook Kang and Seung Cheol Chang, “Procedure for Application of Software Reliability Growth Models to NPP PSA”, Nuclear Engineering and Technology, Vol. 42, No. 8, 2009. 60. Hyun Gook Kang, Heung Sup Eom and Han Seong Son, "Software Failure Probability Quantification for System Risk Assessment", Scholarly research exchange, doi:10.3814/2009/163456, 2009. 61. Hyun Gook Kang, et al., "An Overview of Risk Quantification Issues of Digitalized Nuclear Power Plants using Static Fault Tree", Nuclear Engineering and Technology, Vol. 41, No. 6, 2009. 62. Hyun Gook Kang, et al., "Input-Profile-Based Software Failure Probability Quantification for Safety Signal Generation Systems", Reliability Engineering & System Safety, Vol. 94, No. 10, 2009. 63. Hyun Gook Kang and Seung Cheol Jang, "A Quantitative Study on Risk Issues in Safety Feature Control System Design in Digitalized Nuclear Power Plant",  Journal of Nuclear Science and Technology, Vol. 45, No. 8, 2008. 64. Hyun Gook Kang and Seung Cheol Jang, "Fault Tree-based Risk Assessment for Dynamic Condition Changes",  Nuclear Engineering and Technology, Vol. 39, No. 2, 2007. 65. Hyun Gook Kang, Seung-Cheol Jang and Jejoo Ha, "Fault Tree Modeling for Redundant Multi-Functional Digital Systems", International Journal of Performability Engineering, Vol. 3, No. 3, 2007. 66. Hyun Gook Kang and Seung Cheol Jang, "Plant Risk Effect Analysis Focusing on Digital I＆C Equipment Failures", Journal of Nuclear Science and Technology, Vol. 44, No. 4, 2007. 67. Hyun Gook Kang and Seung-Cheol Jang, "Application of Condition-based HRA Method for a Manual Actuation of the Safety Features in a Nuclear Power Plant", Reliability Engineering & System Safety, Volume 91, Issue 6, June 2006. 68. Suk Joon Kim, Poong Hyun Seong, Jun Seok Lee, Man Cheol Kim, Hyun Gook Kang and Seung Cheol Jang, "A Method for Evaluating Fault Coverage using Simulated Fault Injection for Digitalized Systems in Nuclear Power Plants", Reliability Engineering & System Safety, Volume 91, Issue 5, May 2006. 69. Jun Seok Lee, Man Cheol Kim, Poong Hyun Seong, Hyun Gook Kang and Seung Cheol Jang, "Evaluation of Error Detection Coverage and Fault-tolerance of Digital Plant Protection System in Nuclear Power Plants", Annals of Nuclear Energy, Volume 33, March 2006. 70. Hyun Gook Kang and Seung Cheol Jang, "ATWS Frequency Quantification Focusing on Digital I&C Failures", Journal of Korean Nuclear Society, Vol. 36, No. 2, 2004. 71. Chang-Kue Park, Woo Sik Jung, Joon-Eon Yang, Hyun Gook Kang, Aybars Grpinar and Sok-Chul Kim, "A PSA-based Vital Area Identification Methodology Development", Reliability Engineering & System Safety, Volume 82, Issue 2, November 2003. 72. Hyun Gook Kang and Taeyong Sung, "An Analysis of Safety-Critical Digital Systems for Risk-Informed Design", Reliability Engineering and System Safety, Vol. 78, 2002. 73. Hyun Gook Kang and Taeyong Sung, "A Quantitative Study on Important Factors of the PSA of Safety-Critical Digital Systems", Journal of Korean Nuclear Society, Vol. 33, No. 6, 2001. 74. Hyun Gook Kang and Poong H. Seong, "Information Theoretic Approach to Man-Machine Interface Complexity Evaluation", IEEE Trans. on System, Man and Cybernetics, Part A, Vol. 31, No. 3, pp. 163-171, May 2001. 75. Hyun Gook Kang and Poong H. Seong, "A Methodology for Evaluating Alarm-processing Systems using Informational Entropy-Based Measure and the Analytic Hierarchy Process", IEEE Trans. on Nuclear Science, Vol. 46, No. 6, 1999. 76. Hyun Gook Kang, Poong H. Seong, et al., "Development of Automatic Reactor Internal Vibration Monitoring System Using Fuzzy Peak Detection and Vibration Mode Decision Method", Journal of Korean Nuclear Society, Vol. 30, No. 1, 1998. 77. Hyun Gook Kang and Poong H. Seong, "An Information Theory Based Approach for Quantitative Evaluation of User Interface Complexity", IEEE Trans. on Nuclear Science, Vol. 45, No. 6, 1998. 78. Hyun Gook Kang and Poong H. Seong, "Development of A Real-Time Thermal Performance Diagnostic Monitoring System Using Self-Organizing Neural Network for KORI-2 Nuclear Power Unit",  Journal of Korean Nuclear Society, Vol. 28/1, February 1996. 79. Hyun Gook Kang and Poong H. Seong, "A Real Time Monitoring System of CSB Vibration Using FEM Data & Self-organizing Neural Networks", Nuclear Engineering and Design, Vol. 158/1, 1995. 80. Seong H. Kim, Hyun Gook Kang, et al., "Monitoring of Vibration of Reactor Internals Using Excore Neutron Signals of Younggwang NPP Unit 3, in Korea", Journal of Korean Society of Noise and Vibration Engineering, Vol. 5, No. 3, 1995. 81. Hyun Gook Kang and Poong H. Seong,"Application of Smart Transmitter Technology in Nuclear Engineering Measurements", Journal of Korean Nuclear Society, Vol.25, No.3, 1993.

Teaching

Modeling and Analysis of

Uncertainty

ENGR 2600 Appreciation and understanding of uncertainties and the conditions under which they occur, within the context of the engineering problem-solving pedagogy of measurements, models, validation, and analysis. Problems and concerns in obtaining measurements; tabular and graphical organization of data to minimize misinformation and maximize information; and development and evaluation of models. Concepts will be supported with computer demonstration. Applications to problems in engineering are emphasized. Prerequisite: MATH 1010.          

 

Reactor Reliability and Safety

MANE 6360   MANE 496x Theory and applications of reliability and risk assessment. Boolean algebra, logic diagrams, redundancy, and majority- vote configurations. System synthesis by reliability and fault tree techniques, quantitative evaluation, uncertainty analysis. Common cause events, failure data, and failure models. Allocation of risk to subsystems. Availability, repair policies, renewal theory. Operational reliability methods. Prerequisites: MANE 4050 and MATH 4600

 

Nuclear Power System Engineering

MANE 4400 Application of thermodynamics, heat transfer, and fluid flow principles to nuclear energy generation systems, including nuclear reactors, nuclear fusion devices and systems, and radiation technology. Engineering aspects of 1st and 2nd Laws of Thermodynamics will be emphasized. Characteristics and safety aspects of nuclear power equipment will be discussed. Prerequisites: ENGR2250

Gallery

Location

Address

Lab: JEC Rm 5219 110 Eighth St Troy, NY 12180 USA Office: JEC Rm 5022 110 Eighth St Troy, NY 12180 USA GPS for Visitor Parking 42.729088, -73.676571

Campus Map

Dynamic Risk Assessment

Passive Safety System Operation

Digitalized Plant Risk Assessment