Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 7681 to 7700 of 10376
Role of residual ferrites on crevice SCC of austenitic stainless steels in PWR water with high-dissolved oxygen Sinjlawi, Abdullah; Chen, Junjie; Kim, Ho-Sub; Lee, Hyeon Bae; Jang, Changheui; Lee, Sanghoon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.11, pp.2552 - 2564, 2020-11 |
| Root Cause Finding by Using Google Page Rank Algorithm 채영호; 성풍현, 한국원자력학회 2017 추계발표대회, Korean Nuclear Society, 2017-10-27 |
| Rotation and Transport in MAST Spherical Tokamak Field, Anthony; Michael, Clive; Akers, Rob; Candy, Jeoff; Colyer, Greg; Guttenfelder, Walter; Ghim, Youngchul; et al, 23rd IAEA Fusion Energy Conference, IAEA, 2010-10 |
| Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock Jhung, MJ; Jang, Changheui; Kim, SH; Choi, YH; Kim, HJ; Jung, S; Kim, JM; et al, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.19, no.2, pp.634 - 648, 2005-02 |
| Rule-based finite element modeling system Choi, Chang Koon; Paik Jong-Gyun, Proceedings of the Asian Pacific Conference on Computational Mechanics, pp.1217 - 1221, 1991-12-11 |
| S-CO2 Compressor Performance Test Plan Considering Measurement Accuracy 조성국; 정용주; 이정익, 2019 한국원자력학회 추계학술발표회, 한국원자력학회, 2019-05-23 |
| S-CO2 cycle design and control strategy for the SFR application Ahn, Yoonhan; Kim, Minseok; Lee, Jeong Ik, The 5th International Symposium-Supercritical CO2 Power Cycles, Southwest Research Institute, 2016-03 |
| S-CO2 TURBINE DESIGN FOR DECAY HEAT REMOVAL SYSTEM OF SODIUM COOLED FAST REACTOR Cho, Seong Kuk; Lee, Jekyoung; Lee, Jeong Ik; Cha, Jae Eun, ASME Turbo Expo 2016, ASME, 2016-06-13 |
| SA106Gr.C 주증기 배관재의 피로균열성장에 미치는 후열처리의 영향 김인섭, 국내원전기기의 건전성평가기술 워크샵, 1996 |
| SA508 Gr.3 Cl.2 저합금강과 용접부의 290℃ 수화학 환경에서 피로균열거동 분석 조평연; 김정현; 장창희; 조현철, CORROSION SCIENCE AND TECHNOLOGY, v.11, no.4, pp.120 - 128, 2012-08 |
| SA508 Gr.3 Cl2 저합금강 모재와 용접부의 290oC 순수 환경에서 피로균열거동 분석 장창희; 김정현; 홍종대; 나경환; 이재곤, 2012 한국부식방식학회 춘계학술대회, 사단법인 한국부식방식학회, 2012-05-18 |
| SA508 Gr.3 강의 천이영역 파괴특성에 미치는 응력상태의 영향 = Effect of stress state on the fracture behavior of SA508 Gr.3 steel in the transition regionlink 김석훈; Kim, Seok-Hun; 황용석; 김인섭; et al, 한국과학기술원, 1998 |
| SACS2: A dynamic and formal approach to safety analysis for complex safety critical system Koh, Kwang Yong; Seong, Poong-Hyun, 6th American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2009, v.1, pp.298 - 311, 2009-04-05 |
| SACS2: Dynamic and Formal Safety Analysis Method for Complex Safety Critical System 고광용; 성풍현, 한국원자력학회 2009 춘계학술발표회, 한국원자력학회, 2009-05-21 |
| Safety activities on safety-critical software for reactor protection system Park, G.-Y.; Kwon, K.C.; Jee, E.; Koh, K.Y.; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.96, no.0, pp.237 - 238, 2007 |
| Safety analyses of Kaist Micro modular reactor with modified Gamma+ code Oh, Bong-seong; Lee, Jeong-Ik; Kim, Seong Gu; Yu, Hwanyeal; Moon, Jangsik; Kim, Yonghee; Jeong, Yong Hoon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09 |
| Safety analysis and development of control logic of KAIST Micro Modular Reactor with GAMMA+ code = GAMMA+ 코드를 이용한 초소형 모듈원전의 안전해석 및 제어논리 개발link Oh, Bong Seong; Lee, Jeong Ik; et al, 한국과학기술원, 2017 |
| Safety Analysis of Compacted Spent Fuel with Natural Convection Flow Lee, Kun Jai, ENS/ANS Transactions (ENC 86), pp.741 - 746, 1986 |
| Safety analysis of compacted spent fuel with natural convection flow = 자연 대류시 밀집된 사용후 핵연료 저장조에서의 안전성 분석link Lee, Chang-Ju; 이창주; et al, 한국과학기술원, 1986 |
| Safety analysis of LOCA, transients and tritium permeation in hydrogen production HTGR : 수소 생산 고온 가스로의 LOCA, 천이 및 삼중수소 투과에 대한 안전해석연구 = 수소 생산 고온 가스로의 LOCA, 천이 및 삼중수소 투과에 대한 안전해석연구link , 한국과학기술원, 2012 |
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