| 1641 | Development of a Novel BiO-rGO Composite with Enhanced Capture of Iodine Gas Ng Yuen Hing, Chee Tien Shee; 류호진, 한국원자력학회 2022 춘계학술발표회, 한국원자력학회, 2022-05-19 |
| 1642 | Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis 한상민; 이승민; 성풍현, 한국원자력학회 2015 춘계발표대회, 한국원자력학회, 2015-05-07 |
| 1643 | Development of a Position Decoding ASIC for PET using Silicon Photomultiplier Cho, Gyuseong; Cho, M; Lim, K; Kim, M; Kim, G, IEEE Nuclear Science Syposium and Medical Imaging Conference, IEEE Nuclear Science Syposium and Medical Imaging Conference, 2015-11-01 |
| 1644 | Development of a Position Decoding ASIC for SPECT using Silicon Photomultiplier Cho, Gyuseong; Cho, M; Kim, H; Lim, Kyung Taek, International Workshop on Radiation Imaging Detectors, International Workshop on Radiation Imaging Detectors, 2015-06-30 |
| 1645 | Development of a probabilistic fracture mechanics code for primary system pipes and application for RI-ISI Jang, Changheui; Datta, D.; Yang, J.-S., ASME 2008 Pressure Vessels and Piping Conference, PVP2008, pp.439 - 446, 2008-07-27 |
| 1646 | Development of a Qualitative Evaluation Method Using MFM for Abnormal Conditions HPSI pump in NPPs 노영규; 김승근; 성풍현, 한국원자력학회 2014 추계발표대회, 한국원자력학회, 2014-10-31 |
| 1647 | Development of a quantitative analysis method for dynamic reactor trip signal generation failure in nuclear power plants Shin, S.K.; Seong, Poong-Hyun, 7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2010, NPIC and HMIT 2010, pp.1256 - 1265, 2010-11-07 |
| 1648 | Development of a Quantitative Method for Effort Evaluating the Effect of Cyber Security Control Applications on SDLC in NPPs 이찬영; 성풍현, 한국원자력학회 2018 춘계학술발표회, 한국원자력학회, 2018-05-18 |
| 1649 | Development of a Quantitative Method for Evaluating Cybersecurity Incident Response Capability based on the NPP Cyber Kill-Chain Model 이찬영; 성풍현, 한국원자력학회 2020 춘계학술발표회, 한국원자력학회, 2020-07-09 |
| 1650 | Development of a Quantitative Method for Evaluating Security Controls Based on Intrusion Tolerant Concept: Consideration of Adverse Effects Lee, Chanyoung; Seong, Poong-Hyun, ISOFIC 2017, Korean Nuclear Society, 2017-11-28 |
| 1651 | Development of a Quantitative Method for Evaluating the Efficacy of Cyber Security Controls in NPPs Based on Intrusion Tolerant Concept 이찬영; 성풍현, 한국원자력학회 2017 춘계학술발표회, Korean Nuclear Society, 2017-05-19 |
| 1652 | Development of a Reactor Vessel Failure Diagnosis System for Accident Management No, CH; Chang, Soon-Heung, International Conference on Probabilistic Safety Assessment Methodology and Applications, 1995 |
| 1653 | Development of a Real-time Interactive Nuclear Power Plant Accident Simulation Using Supervised Learning 송석호; 이연하; 이정익, 한국원자력학회 2022춘계학술발표회, 한국원자력학회, 2022-05 |
| 1654 | Development of a Scaling Factor Prediction Method for Radionuclide Composition in Low-Level Radioactive Waste 이건재, 한국원자력학회 춘계학술발표회, pp.833 - 838, 1995 |
| 1655 | Development of a Scaling Methodology for a Spent Fuel Assembly No, Hee Cheon; Yoo, Seung Hun; Kim, Hyeun Min, 한국원자력학회 추계발표회, 한국원자력학회, 2007 |
| 1656 | Development of a scaling methodology for a spent fuel assembly Yoo, S.H.; Kim, H.M.; No, Hee Cheon, 2007 Winter Meeting on International Conference on Making the Renaissance Real, pp.103 - 104, 2007-11-11 |
| 1657 | Development of a Scaling Methodology for a Spent Fuel Assembly No, Hee Cheon, KNS 2007 Autumn |
| 1658 | Development of a Signal Reconstruction Model for NPPs under Emergency Situation Kim, Seung Geun; Seong, Poong-Hyun, 2019 ANS Annual Meeting, American Nuclear Society, 2019-06-13 |
| 1659 | Development of a Situation Assessment Model of a Nuclear Power Plant Operator from Compact Nuclear Simulator Simulations Kim, Man Cheol; Seong, Poong-Hyun, 한국원자력학회 2005 춘계학술발표대회, 한국원자력학회, 2005-05-26 |
| 1660 | Development of a Smith-Purcell Type Free Electron Laser Cho, Sung Oh; Lee, Byung Cheol; Jeong, Young Uk; Kim, Sun Kook; Lee, Jongmin, Proceedings of 4th Asian Symposium on Free Electron Lasers, 1999 |
