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

Showing results 7761 to 7780 of 10268

7761
Signal Generation due to Alpha Particle in Hydrogenated Amorphous Silicon Radiation Detectors

Kim, HoKyung; Cho, Gyu-Seong, NUCLEAR ENGINEERING AND TECHNOLOGY , v.28, no.4, pp.397 - 404, 1996-06

7762
SIGNAL GENERATION IN A HYDROGENATED AMORPHOUS-SILICON DETECTOR

QURESHI, S; PEREZMENDEZ, V; KAPLAN, SN; FUJIEDA, I; Cho, Gyuseong; STREET, RA, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.36, no.1, pp.194 - 198, 1989-02

7763
Signal pattern matching and automated algorithms for the loose parts monitoring system of the nuclear power plant = 원자력발전소 금속파편감시계통 신호의 패턴매칭과 자동화 알고리듬에 관한 연구link

Chang, Young-Woo; 장영우; et al, 한국과학기술원, 2003

7764
SIGNAL READOUT IN A-SIH PIXEL DETECTORS

Cho, Gyuseong; DREWERY, JS; HONG, WS; JING, T; KAPLAN, SN; LEE, H; PEREZMENDEZ, V; et al, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.4, pp.323 - 327, 1993-08

7765
Signal to noise ratio of upgraded imaging bolometer for KSTAR

Peterson, Byron J.; Oh, Seungtae; Seo, Dongcheol; Jang, Juhyeok; Park, Jae Sun; Mukai, Kiyofumi; Choe, Wonho, REVIEW OF SCIENTIFIC INSTRUMENTS, v.89, no.10, pp.10E115, 2018-10

7766
Signal-dependent independent component analysis by tunable mother wavelets = 튜닝 가능한 마더 웨이블릿으로 신호의 특성을 반영한 독립요소분석 기법link

Seo, Kyung-Ho; 서경호; et al, 한국과학기술원, 2006

7767
Signed-Digraph 를 이용한 가압기 고장진단

박주현; 성풍현, 한국원자력학회 '93 춘계 학술발표회 , pp.355 - 360, 한국원자력학회, 1993-05

7768
Significance of domestic specific input data for improving their reliability and applicability for safety assessment of radioactive waste disposal

윤종일, 2017 한국방사성폐기물학회 추계학술발표회, 한국방사성폐기물학회, 2017-10-18

7769
Significance of International Guideline for the Safety of Computer-Based Systems for NPP from Organizational Aspect

Yoshikawa, H.; Miyazawa, T.; Oh, S.R.; Seong, Poong-Hyun; Nakanishi, S.; Makino, S.; Ohga, Y.; et al, International Conference on "Universal Access in Human - Computer Interaction (UAHCI), 2001-08

7770
Significant ion acceleration of Xe ions outside the discharge channel in cylindrical Hall thruster plasmas observed by laser induced fluorescence

Doh, Guentae; Kim, Holak; Lee, Dongho; Park, Sanghoo; Yoon, Sung-young; Choe, Wonho, 36th International Electric Propulsion Conference (IEPC), University of Vienna, 2019-09-19

7771
Sigular Points and Hyperbolicity Breaking in Two-Phase Flow

노희천; 이재영, 한국원자력학회 추계발표회, 한국원자력학회, 1990

7772
Silicon photomultiplier modules for MRI-compatible PET

Sul, Woo-Suk; Kim, Hyoungtaek; Cho, Gyuseong, JOURNAL OF INSTRUMENTATION, v.10, 2015-04

7773
Silver hierarchical bowl-like array: Synthesis, superhydrophobicity, and optical properties

Li, Yue; Li, Cuncheng; Cho, Sung Oh; Duan, Guotao; Cai, Weiping, LANGMUIR, v.23, no.19, pp.9802 - 9807, 2007-09

7774
Similitude models for turbine off-design performance prediction under supercritical CO2 condition

정용주; 손성민; 조성국; 이정익, 2019 KNS 추계학술발표회, 한국원자력학회, 2019-10-24

7775
Simple analysis of an External Vessel Cooling Thermosyphon for a Sodium-cooled Fast Reactor

최재영; 송섭리; 정용훈, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2015-05-08

7776
Simple Measure of Uncertainty Importance Using Entire Change of Cumulative Distribution Functions

Chun, Moon Hyun, Proc. of the International Topical Meeting on Probabilistic Safety Assessment (PSA99), pp.269 - 278, 1999

7777
Simple microwave preionization source for ohmic plasmas

Choe, Wonho; Kwon, GC; Kim, J; Kim, J; Jeon, SJ; Huh, S, REVIEW OF SCIENTIFIC INSTRUMENTS, v.71, no.7, pp.2728 - 2732, 2000-07

7778
Simple models for jet breakup length and fraction of particulate debris estimation

Kim, Jegon; No, Hee-Cheon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09-05

7779
Simplification in Advanced Reactor Designs

Golay, MW; Manno, VP; Seong, Poong-Hyun, A.N.S. Topical Meeting on Safety of Next Generation Power Reactors, 1988

7780
Simplification of Nuclear Power Station Designs

Golay, MW; Manno, VP; Seong, Poong-Hyun, U.S. NRC Light Water Reactor Safety Conference, 1987

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