Folgen
Jaehyun CHO
Jaehyun CHO
Bestätigte E-Mail-Adresse bei cau.ac.kr
Titel
Zitiert von
Zitiert von
Jahr
PASCAR: Long burning small modular reactor based on natural circulation
S Choi, JH Cho, MH Bae, J Lim, D Puspitarini, JH Jeun, HG Joo, ...
Nuclear Engineering and Design 241 (5), 1486-1499, 2011
722011
Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation
YH Shin, S Choi, J Cho, JH Kim, IS Hwang
Progress in Nuclear Energy 83, 433-442, 2015
452015
Benchmarking of thermal hydraulic loop models for Lead-Alloy Cooled Advanced Nuclear Energy System (LACANES), phase-I: Isothermal steady state forced convection
JH Cho, A Batta, V Casamassima, X Cheng, YJ Choi, IS Hwang, J Lim, ...
Journal of nuclear materials 415 (3), 404-414, 2011
402011
Development of a Bayesian belief network model for software reliability quantification of digital protection systems in nuclear power plants
HG Kang, SH Lee, SJ Lee, TL Chu, A Varuttamaseni, M Yue, S Yang, ...
Annals of Nuclear Energy 120, 62-73, 2018
332018
URANUS: Korean lead-bismuth cooled small modular fast reactor activities
S Choi, IS Hwang, JH Cho, CB Shim
Small modular reactors symposium 54730, 107-112, 2011
252011
Optimization of software development life cycle quality for NPP safety software based on a risk-cost model
SH Lee, SJ Lee, SR Koo, A Varuttamaseni, M Yue, M Li, J Cho, HG Kang
Annals of Nuclear Energy 135, 106961, 2020
232020
Application of a deep learning technique to the development of a fast accident scenario identifier
H Kim, J Cho, J Park
IEEE Access 8, 177363-177373, 2020
202020
Technical challenges in modeling human and organizational actions under severe accident conditions for Level 2 PSA
J Kim, J Cho
Reliability Engineering & System Safety 194, 106239, 2020
192020
Quantification of LOCA core damage frequency based on thermal-hydraulics analysis
J Cho, JH Park, DS Kim, HG Lim
Nuclear Engineering and Design 315, 77-92, 2017
182017
Probabilistic deep learning model as a tool for supporting the fast simulation of a thermal–hydraulic code
S Ryu, H Kim, SG Kim, K Jin, J Cho, J Park
Expert Systems with Applications 200, 116966, 2022
152022
Exhaustive simulation approach for severe accident risk in nuclear power plants: OPR-1000 full-power internal events
J Cho, SH Lee, YS Bang, S Lee, SY Park
Reliability Engineering & System Safety 225, 108580, 2022
142022
Realistic estimation of human error probability through Monte Carlo thermal-hydraulic simulation
J Cho, Y Kim, J Kim, J Park, DS Kim
Reliability Engineering & System Safety 193, 106673, 2020
132020
Experimental studies and computational benchmark on heavy liquid metal natural circulation in a full height-scale test loop for small modular reactors
YH Shin, J Cho, J Lee, H Ju, S Sohn, Y Kim, H Noh, IS Hwang
Nuclear Engineering and Design 316, 26-37, 2017
132017
Framework to model severe accident management guidelines into Level 2 probabilistic safety assessment of a nuclear power plant
J Cho, SH Lee, J Kim, SK Park
Reliability Engineering & System Safety 217, 108076, 2022
102022
Natural circulation characteristics under various conditions on heavy liquid metal test loop
KH Ryu, BM Ban, TH Lee, J Lee, SH Lee, JH Cho, S Ko, JH Kim
International Journal of Thermal Sciences 132, 316-321, 2018
102018
Application of a process mining technique to identifying information navigation characteristics of human operators working in a digital main control room–feasibility study
J Park, JY Jung, G Heo, Y Kim, J Kim, J Cho
Reliability Engineering & System Safety 175, 38-50, 2018
102018
Identification of risk-significant components in nuclear power plants to reduce Cs-137 radioactive risk
J Cho, SH Han
Reliability Engineering & System Safety 211, 107613, 2021
92021
Exhaustive test cases for the software reliability of safety-critical digital systems in nuclear power plants
J Cho, SM Shin, SJ Lee, W Jung
Nuclear Engineering and Design 352, 110151, 2019
82019
Development of transportable capsule version of PEACER design
IS Hwang, MH Kim, HG Joo, B Yoo, MH Kim, SR Oh, KW Yi, DY Han, ...
ICAPP 8, 8-12, 2008
82008
Bayesian belief network model quantification using distribution-based node probability and experienced data updates for software reliability assessment
SJ Lee, SH Lee, TL Chu, A Varuttamaseni, M Yue, M Li, J Cho, HG Kang
IEEE Access 6, 64556-64568, 2018
72018
Das System kann den Vorgang jetzt nicht ausführen. Versuchen Sie es später erneut.
Artikel 1–20