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

Showing results 8801 to 8820 of 10372

8801
Theoretical and experimental studies on the solubility of magnetite = 마그네타이트의 용해도에 관한 이론 및 실험적 연구link

Chung, Jin-Yop; 정진엽; et al, 한국과학기술원, 1987

8802
Theoretical Background and Case Study for the Exergo-economic Optimization of a Large-scale Electricity Storage System using supercritical Carbon Dioxide

Py, Baptiste; Jeong, Yong Hoon, 2019 ANS Winter Meeting and Nuclear Technology EXPO, American Nuclear Society, 2019-11-18

8803
Theoretical design of the target for a CNT-based high-brightness microfocus X-ray tube

조성오; Ihsan, Aamir, 한국물리학회 (2005년 가을 논문발표회), pp.594 -, 한국물리학회, 2005

8804
Theoretical Detective Quantum Efficiency(DQE) of CMOS Image Sensor Coupled with MCP (microchannel plate) in Low Energy X-ray

Cho, Gyuseong; Chi, Y.K.; Ahn, S.K.; Kim, Y.S., IEEE Nuclear Science Symposium and Medical Imaging Conference, 2004

8805
Theoretical Estimation of Source Term in Reactor Coolant System.

Lee, Kun Jai, Int'l Workshop on "Determination and Declaration on Nuclide Specific Activity Inventoriesin Radioactive Wastes.", 2001

8806
THEORETICAL INVESTIGATION OF VAPOR BLANKET VELOCITY BASED ON MASS, ENERGY, AND MOMENTUM BALANCE TO PREDICT CHF AT LOW QUALITY FLOW

LEE, YB; BAEK, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.19, no.5, pp.619 - 628, 1992

8807
Theoretical Study on the Estimation of Nuclear Resonance Fluorescence Cross Sections = 핵공명형광(NRF) 반응단면적의 이론적 평가 방법 연구link

Ju, Kwangho; Kim, Yonghee; et al, 한국과학기술원, 2019

8808
Theoretical Study on the Migration Phenomena of a Chelated Radionuclide in a Porous Medium

Lee, Kun Jai, Waste Management '93, pp.1723 - 1728, 1993

8809
Thermal Aging Embrittlement of High Chromium Oxide Dispersion Strengthening Steels

Lee, J.S; Kim, In Sup; Jang, Changheui; Kimura, A.; Kim, B.G.; Choo, KN; Choo, Y.S; et al, 한국원자력학회 2005년도 춘계학술발표회, pp.471 - 472, 한국원자력학회, 2005-05-26

8810
Thermal Aging Embrittlement of High Cr Oxide Dispersion Strengthened Steels

Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., ICFRM-12, 2005-12-07

8811
Thermal analysis and design of dry storage cask of spent nuclear fuel = 사용 후 핵연료 건식 저장 용기의 열해석 및 설계link

Kim, Jung-Ho; 김중호; et al, 한국과학기술원, 2009

8812
Thermal analysis mode of the CANDU fuel bundle in a dry storage canister = 건식저장조에서의 사용후 핵연료 집합체에 대한 열해석link

Choi, Hae-Yun; 최해윤; et al, 한국과학기술원, 1996

8813
Thermal analysis of dry concrete canister storage system for CANDU spent fuel = CANDU 사용후 핵연료 건식저장시설에 대한 열해석link

Ryu, Yong-Ho; 류용호; et al, 한국과학기술원, 1992

8814
Thermal Analysis of Wolsung Unit 1 (CANDU) Spent Fuel Dry Storage Canister

Chun, Moon Hyun, 16th Biennial ANS Topical Meeting on Reactor Operations Experience, pp.98 - 104, 1993

8815
Thermal and Mechanical Stability Analysis of the Transmission Target of a CNT-Based Microfocus X-ray Tube

Cho, Sung Oh; IHSAN, Aamir; HEO, Sung Hwan, 한국물리학회 (2006년 가을 논문발표회), pp.527 - 528, 한국물리학회, 2006

8816
Thermal and stress analysis of a fuel pellet using the finite element method = 유한요소법을 이용한 핵연료 페레트의 온도 및 응력 해석link

Jeong, Jong-Tae; 정종태; et al, 한국과학기술원, 1986

8817
Thermal conductivity modeling of the interaction layer of the irradiated U-Mo dispersion fuel

Mistarihi, Qusai; 류호진, 한국원자력학회 2018 춘계학술발표회, 한국원자력학회, 2018-05-17

8818
Thermal conductivity of Mo-reinforced ZrO2 composites fabricated by spark plasma sintering for inert matrix fuels

Mistarihi, Qusai M.; Raj, Vivek; Kim, Joon Hui; Ryu, Ho Jin, MATERIALS AND DESIGN, v.134, pp.476 - 485, 2017-11

8819
Thermal coupling of HTGR and desalination system, and performance and cost analysis = 고온가스냉각로를 기반으로 한 전기 및 담수생산용 통합시스템의 최적설계 및 안전해석과 성능 및 경제성 분석 프로그램 개발link

Kim, Ho-Sik; 김호식; et al, 한국과학기술원, 2011

8820
Thermal coupling of HTGRs and MED desalination plants, and its performance and cost analysis for nuclear desalination

Kim, Ho Sik; No, Hee Cheon, DESALINATION, v.303, pp.17 - 22, 2012-10

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