Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title

Showing results 6461 to 6480 of 8729

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; 장창희researcher; 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

장창희researcher; 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-Hyunresearcher, 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; 성풍현researcher, 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-Hyunresearcher, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.96, no.0, pp.237 - 238, 2007

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 Jairesearcher, 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 HTGRlink

, 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 Cheonresearcher; Kim, Ho Sik; Jin, Hyung Gon, American Nuclear Society, 2010-06

Safety Analysis of VHTRs with MED Desalination Plants

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

Safety Analysis Using Coloured Petri Nets

Cho, Seung Mo; Hong, Hyoung Seok; Cha, Sungdeok, Asia-Pacific Software Engineering Conference, pp.176 - 183, IEEE, 1996-12-04

Safety Assessment and Public Acceptance of Nuclear in Korea

Kang, Hyun Gookresearcher, IYNC 2002, 2002

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-Heungresearcher, 한국원자력학회 2002년도 춘계공동학술발표회, 한국원자력학회, 2002

Safety case of digital protection systems focusing on safety-critical software failures in NPP = 안전 소프트웨어의 오류 평가를 중심으로 한 원전 디지털 계통 안전 케이스 개발link

Kim, Hee Eun; Kang, Hyun Gook; et al, 한국과학기술원, 2018

Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident

Kim, Sang Ho; Futami, Tsuneo; Chang, Soon-Heungresearcher; Jeong, Yong Hoonresearcher, SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, v.520756, 2015-02

Safety evaluation of supercritical CO2 cooled micro modular reactor

Oh, Bong Seong; Ahn, Yoon Han; Yu, Hwanyeal; Moon, Jangsik; Kim, Seong Gu; Cho, Seong Kuk; Kim, Yongheeresearcher; et al, ANNALS OF NUCLEAR ENERGY, v.110, pp.1202 - 1216, 2017-12



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