8041 | Status and plan of shattered pellet injection in KSTAR for studying ITER disruption mitigation Kim, J; Park, SH; Jang, JH; Baylor, LR; Kim, KP; Kim, JH; Yun, GS; et al, KSTAR Conference 2019, National Fusion Research Institute, 2019-02-21 |
8042 | STATUS AND PLAN OF THE SYSTEM CODES DEVELOPMENT FOR ITER TEST BLANKET MODULE AND FUSION BREEDING BLANKET IN KOREA Lee, Dong-Won; Yum, Soo-Been; Park, Goon-Cherl; Kim, Seol-Ha; Kim, Moo-Hwan; Jin, Hyung-Gon; No, Hee-Cheon; et al, FUSION SCIENCE AND TECHNOLOGY, v.64, no.3, pp.645 - 650, 2013-09 |
8043 | Status and Progress of Development of Radionuclide Inventory Declaration Method for the Disposal of Radwaste in Korea Lee, Kun Jai, IAEA Int'l Conf. on the Safety of Radioactive Waste Disposal, 2005 |
8044 | Status and prospects of a compact FIR FEL driven by a magnetron-based microtron Jeong, YU; Kazakevitch, GM; Lee, BC; Kim, SK; Cho, Sung Oh; Gavrilov, NG; Lee, J, NUCLEAR INSTRUMENTS METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, v.483, no.1-2, pp.195 - 199, 2002-05 |
8045 | Status of Free-Electron Laser Projects at KAERI Cho, Sung Oh; Lee, Byung Cheol; Jeong, Young Uk; Yoo, Jaegwon, Proceedings of Asian Particle Accelerator Conference, 2001 |
8046 | Status of KAERI Electron Beam Irradiators Cho, Sung Oh; Lee, Byung Cheol; Jeong, Young Uk, IAEA, Proceedings of international symposium on utilization of accelerators, 2001 |
8047 | Status of Low-Level Radioactive Waste Management in Korea Lee, Kun Jai, Fourteenth Annual U.S. DOE Low-Level Radioactive Waste Management Conference, pp.18 - 20, 1992 |
8048 | Status of Managing the Tritium Generated from Heavy Water Reactors in Korea Lee, Kun Jai, Int'l Low-Level Waste Conference & Exhibit Show by EPRI, 2000 |
8049 | Status of Nuclear Fuel Cycle Options and Spent Fuel Management in Korea Ryu, Ho Jin; Song, Kee Chan; Park, HS, Meeting of Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management, IAEA, 2007-10 |
8050 | Status of Operation of Radionuclide Assay System in Korean Nuclear Power Plant Lee, Kun Jai, RADWAP 2002 : 4th Int'l Seminar on Radioactive Waste Products, 2002 |
8051 | Status of Oxide Dispersion Strengthened High Entropy Alloys Development 정승혁; 류호진, 한국원자력학회 2017 춘계학술대회, 한국원자력학회, 2017-05-18 |
8052 | Status of the Tririum related Activitiesin Korea and Preliminary Study on the Integrity of Tritium Storage Vessel. Lee, Kun Jai, TRITIUM 2001: 6th Int'l Conf. on Tritium Science and Technology., 2001 |
8053 | Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model Lee, Yoonhee; Cho, Nam-Zin, ANNALS OF NUCLEAR ENERGY, v.76, pp.283 - 296, 2015-02 |
8054 | Steady- and Transient-State Analyses of Fully Ceramic Microencapsulated Fuel with Randomly Dispersed Tristructural Isotropic Particles via Two-Temperature Homogenized Model-I: Theory and Method Lee, Yoonhee; Cho, Bumhee; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.650 - 659, 2016-06 |
8055 | Steady- and Transient-State Analyses of Fully Ceramic Microencapsulated Fuel with Randomly Dispersed Tristructural Isotropic Particles via Two-Temperature Homogenized Model-II: Applications by Coupling with COREDAX Lee, Yoonhee; Cho, Bumhee; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.660 - 672, 2016-06 |
8056 | Steady- and transient-state analysis methodology of fully ceramic microencapsulated fuel via two-temperature homogenized model = 두 온도 균질화법에 의한 Fully Cermaic Microencapsulated (FCM) 핵연료의 정상 및 과도상태 해석 방법link Lee, Yoonhee; 이윤희; et al, 한국과학기술원, 2016 |
8057 | Steam condensation heat transfer in the presence of noncondensables in a vertical tube of passive containment cooling system = 피동격납용기 냉각계통의 수직 응축관 내부에서의 불응축성기체 존재하의 증기응축 열전달link Park, Hyun-Sik; 박현식; et al, 한국과학기술원, 1999 |
8058 | Steam cycle optimization study of thermal energy storage for nuclear power plants responding to renewable energy = 재생에너지 대응 원자력 발전소 열에너지 저장 증기 사이클 최적화 연구link Lee, Ju Yeon; Lee, Jeong Ik; et al, 한국과학기술원, 2020 |
8059 | Steam Generator Tube Rupture Accident at a NPP and Exploration of Mitigation Strategies for Its Consequence Ullah, Sana; 강성우; 왕웅재; 변현호; 임만성, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-17 |
8060 | Steam Removal Phenomenon Inside the Containment of Nuclear Power Plants using Silica Gel Considering Initial Steam Partial Pressure Conditions Up to a Design Limit 감동훈; 정용훈, 2019 한국원자력학회 춘계학술발표회, 한국원자력학회, 2019-05-23 |