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

Showing results 8661 to 8680 of 10268

8661
The Statistical Analysis for the Characteristics of Low-Level Wastes Generated from PWR

이건재, 한국원자력학회 학술발표회 ( 춘계 ), pp.505 - 524, 1991

8662
The Study of the Gamma Energy Identifying Algorithm with the Noise Reduction Method for a Compact Radiation Sesnsor

Yoo, H; Cho, Gyuseong; Kim, Y; Kim, M; Lim, Kyung Taek, IEEE Symposium On Radiation Measurements and Applications, IEEE Symposium On Radiation Measurements and Applications, 2016-05-25

8663
The Study on the Magnetic Filter using the Rotation of Permanent Magnets for Separation of Radioactive Corrosion Products

Lee, Kun Jai, Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2003, 2003

8664
The Synergetic Effects of a Nuclear-Assisted Gas Turbine Power Cycle

Jeong, Yong Hoon; Saha, Pradip; Kazimi, Mujid S., American Nuclear Society 2004 Winter Meeting, 2004-11-14

8665
The synergetic effects of nuclear-assisted gas turbine power cycles

Jeong, Yong Hoon; Kazimi, Mujid S., NUCLEAR TECHNOLOGY, v.160, no.2, pp.233 - 243, 2007-11

8666
The Synthesis and Analysis of WxTaTiVCr Alloy for High Temperature and Plasma Facing Applications

Waseem, Owais Ahmed; Ryu, Ho Jin; Kim, Seung Su; Hong, Soon Hyung, The Nuclear Materials Conference, Elsvier, 2016-11-08

8667
The Synthesis and Characterization of W- 1wt. % TiC Alloy Using a Chemical Method

Ryu, Ho Jin; Kim, Tae Hee, 한국분말야금학회 2016 추계학술대회, 한국분말야금학회, 2016-11-10

8668
The Transient Thermal Analysis at a Nuclear Containment Wall during LOCA for an Analysis of a PCM Behavior

최요나단; 정용훈, 2020 한국원자력학회 춘계학술발표회, 한국원자력학회, 2020-07-09

8669
THE TRINOMIAL FAILURE RATE MODEL FOR TREATING COMMON-MODE FAILURES

HAN, SG; YOON, WH; Chang, Soon-Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.25, no.2, pp.131 - 146, 1989

8670
The Two Step Characteristic Method to Reduce Numerical Diffusion

Golay, MW; Chang, Soon-Heung, 1983 American Nuclear Society Mathematics and Computation Topical Meeting, American Nuclear Society, 1983

8671
The use of atmospheric pressure plasma-treated water as a source of nitrite for emulsion-type sausage

Jung, Samooel; Kim, Hyun Joo; Park, Sanghoo; Yong, Hae In; Choe, Jun Ho; Jeon, Hee-Joon; Choe, Wonho; et al, MEAT SCIENCE, v.108, pp.132 - 137, 2015-10

8672
The Use of Burnup Credit in Criticality Control for the Korean Spent Fuel Management Program

Koh, D.J; Jo, C.K; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.245 - 250, 1997

8673
The Validation and Verification of Gas System Analysis Code GAMMA+ with S-CO2 Compressor Test Data

Bae, Seong Jun; Ahn, Yoon Han; Lee, Jeong Ik, The Korean Nuclear Society Autumn Meeting(2014), The Korean Nuclear Society, 2014-10

8674
(The) analysis of energy security costs considering the dynamics of technology innovation : case study of the United Arab Emirates = 기술 혁신 역학을 고려한 에너지 안보 비용 분석 : UAE의 사례 연구link

Al Shehhi, Ahmed Saeed; 임만성; et al, 한국과학기술원, 2020

8675
(The) analysis of fuel rod behavior using finite element method = 유한요소법을 이용한 핵연료 거동 분석link

Park, Young-Seob; 박영섭; et al, 한국과학기술원, 1988

8676
(The) behaviors of implanted deuterium in titanium = 티타늄에 주입된 중수소의 거동link

Lee, Byung-Ho; 이병호; et al, 한국과학기술원, 1991

8677
(The) conceptual design support system based on scale laws for liquid metal reactors = Scale law에 근거한 액체 금속로의 개념 설계 지원시스템에 관한 연구link

Lee, Kwang-Gu; 이광구; et al, 한국과학기술원, 1997

8678
(The) derivation of dryout model in a particle debris-bed with drift-flux approach = 편류속 방법에 의한 노심 파편층에서 건조열속 모형의 유도link

Kim, Seong-Ho; 김성호; et al, 한국과학기술원, 1985

8679
(The) derivation of the closed form solution for two-phase mixture level and collapsed liquid level in a boil-off transient = 과도증발사고시 이상혼합체 수위와 기포 제거 수위에 대한 폐쇄형 해의 유도link

Jin, Jeong-Soo; 진정수; et al, 한국과학기술원, 1986

8680
(The) development of an alarm filtering system for pressurizer = 가압기 고장 진단 전문가 시스템의 개발link

Park, Hee-Seok; 박희석; et al, 한국과학기술원, 1989

Discover

Type

Open Access

Date issued

Subject

. next

rss_1.0 rss_2.0 atom_1.0