Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 7681 to 7700 of 10372
| 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 |
| Safety analysis of safety-critical software for nuclear digital protection system Park G.-Y.; Lee J.-S.; Cheon S.-W.; Kwon K.-C.; Jee, Eunk Young; Koh K.Y., 26th International Conference on Computer Safety, Reliability, and Security, SAFECOMP 2007, v.4680, pp.148 - 161, 2007-09-18 |
| Safety Analysis of VHTRs with MED Desalination Plants No Hee Cheon; Kim, Ho Sik; Jin, Hyung Gon, American Nuclear Society, 2010-06 |
| Safety Analysis of VHTRs with MED Desalination Plants No, Hee Cheon; Kim, Ho Sik; Jin, Hyung Gon, American Nuclear Society, v.104, 2011-06 |
| Safety and performance enhanced boehmite-coupled polyethylene nanocomposite separator for lithium-ion batteries by synergetic effects of silane treatment and electron irradiation = 전자빔 조사를 이용하여 안전성 및 성능이 강화된 베마이트-폴리에틸렌 나노복합재 리튬 이차전지 분리막link Lee, Sang Yoon; Cho, Sung Oh; et al, 한국과학기술원, 2023 |
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