Browse "NE-Conference Papers(학술회의논문)" by Title 

Showing results 4159 to 4178 of 5611

4159
S-CO2 Compressor Performance Test Plan Considering Measurement Accuracy

조성국; 정용주; 이정익, 2019 한국원자력학회 추계학술발표회, 한국원자력학회, 2019-05-23

4160
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

4161
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

4162
SA106Gr.C 주증기 배관재의 피로균열성장에 미치는 후열처리의 영향

김인섭, 국내원전기기의 건전성평가기술 워크샵, 1996

4163
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

4164
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

4165
SACS2: Dynamic and Formal Safety Analysis Method for Complex Safety Critical System

고광용; 성풍현, 한국원자력학회 2009 춘계학술발표회, 한국원자력학회, 2009-05-21

4166
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

4167
Safety Analysis of Compacted Spent Fuel with Natural Convection Flow

Lee, Kun Jai, ENS/ANS Transactions (ENC 86), pp.741 - 746, 1986

4168
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

4169
Safety Analysis of VHTRs with MED Desalination Plants

No Hee Cheon; Kim, Ho Sik; Jin, Hyung Gon, American Nuclear Society, 2010-06

4170
Safety Analysis of VHTRs with MED Desalination Plants

No, Hee Cheon; Kim, Ho Sik; Jin, Hyung Gon, American Nuclear Society, v.104, 2011-06

4171
Safety Assessment and Public Acceptance of Nuclear in Korea

Kang, Hyun Gook, IYNC 2002, 2002

4172
Safety Assessment on Vitrification Facility of Low- and Intermediate-Level Radioactive Wastes

Heo, GY; Lee, SJ; Ji, PG; Maeng, SJ; Park, JG; Shin, SU; Chang, Soon-Heung, 한국원자력학회 2002년도 춘계공동학술발표회, 한국원자력학회, 2002

4173
Safety Improvement with Er Burnable Absorber in CANDU Reactor Loaded with Recovered Uranium Fuel

MOHAMMAD ABDUL; Kim, Yonghee; Kim, Woosong, International Workshop on PHWR Challenging Issue for Safe Operation and Long-term Sustainability (CANSAS), International Workshop on PHWR Challenging Issue for Safe Operation and Long-term Sustainability (CANSAS), 2016-10-12

4174
SAFETY INJECTION TANK PERFORMANCE ANALYSIS USING CFD

Cho, Jai Oan; Addad, Yacine; Lee, Jeong-Ik; Nietiadi, Yohanes Setiawan; Bang, Young Seok; Yoo, Seung Hun, The Korean Nuclear Society Autumn Meeting, The Korean Nuclear Society, 2016-10-27

4175
Safety of Silicon Carbide Cladding for Fail-Safe Simple Economical SMR (FASES)

No, Hee-Cheon; Lee, Youho; Kim, Ho Sik, ANS2014, ANS2014, 2014-06-19

4176
Safety Prediction for Basic Components of Safety-Critical Software Based on Static Testing

Son, Han Seong; Seong, Poong-Hyun, International Youth Nuclear Congress 2000, 2000-04

4177
Safety, Risk, Culture and Public Acceptance of Nuclear in Korea

Kang, Hyun Gook, East-west Youth Cooperation Seminar, 2001

4178
Sampling and Measurement System of Radioactive Aerosols from Metal Cutting with Plasma Arc Torch

Yang, Wonseok; Lee, Minho; Chae, Nakkyu; Choi, Sungyeol, European Aerosol Conference 2019, Nordic Society for Aerosol Research & Gothenburg Air and Climate Network, 2019-08

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