| 200801 | Thermal-hydraulic analysis of annular fuel-based assemblies of liquid metal reactors Han, K.-H.; Chang, Soon-Heung, American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.1, pp.38 - 46, American Nuclear Society, 2005-05-15 |
| 200802 | Thermal-hydraulic analysis of mixed cores with optimized and standard fuel assemblies = 최적 핵연료 집합체와 표준 핵연료 집합체 장전 혼합 노심에 대한 열.수력 해석link Kim, Se-Chang; 김세창; et al, 한국과학기술원, 1985 |
| 200803 | Thermal-hydraulic analysis of the containment for design of passive containment cooling system = 피동 격납용기 냉각계통의 설계를 위한 격납용기의 열-유체 분석link Park, Jong-Ha; 박종하; et al, 한국과학기술원, 1991 |
| 200804 | Thermal-hydraulic Analysis of the GT-MHR Core using Axiomatic Design Jeong, HD; Chang, Soon-Heung, NUTHOS-7, 2008-10-05 |
| 200805 | Thermal-hydraulic characteristics evaluations of the printed circuit heat exchanger in a helium-water test loop Kim, I.H.; No, Hee Cheon, International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.1749 - 1757, 2010-06-13 |
| 200806 | Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop No, Hee Cheon; Kim, In Hun, 한국원자력학회 추계발표회, 한국원자력학회, 2009 |
| 200807 | Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop No, Hee Cheon, the KNS Autumn Meeting |
| 200808 | Thermal-hydraulic design methodology and trade-off studies for a dual-salt breed-and-burn molten salt reactor Kasam, Alisha; Lee, Jeong Ik; Shwageraus, Eugene, NUCLEAR ENGINEERING AND DESIGN, v.360, 2020-04 |
| 200809 | Thermal-hydraulic evaluation of passive containment cooling system of improved APR plus during LOCAs Jeon, Byong Guk; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.278, pp.190 - 198, 2014-10 |
| 200810 | Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs 노희천; 전병국, KNS Spring, KNS Spring, 2014-05-29 |
| 200811 | Thermal-hydraulic experiment and analysis for interim dry storage of spent nuclear fuel = 사용후 핵연료의 중간건식저장에 대한 열유체 실험 및 해석link Yoo, Seung-Hun; 류승훈; et al, 한국과학기술원, 2011 |
| 200812 | Thermal-hydraulic experiments for the PCHE type steam generator 노희천; 신창욱, KNS Spring, KNS Spring, 2015-05-07 |
| 200813 | Thermal-hydraulic performance of a printed circuit heat exchanger in an air test loop = 공기를 이용한 개방형계에서의 인쇄형 열교환기의 열수력학적 실험link Song, Sung-Chu; 송성주; et al, 한국과학기술원, 2006 |
| 200814 | Thermal-Hydraulic Performance Tests of PCHE Using Mixture-Gas for HTGRs No Hee Cheon; Kim, In Hun, American Nuclear Society, 2011-06 |
| 200815 | Thermal-hydraulic physical models for a Printed Circuit Heat Exchanger covering He, He-CO2 mixture, and water fluids using experimental data and CFD Kim, In-Hun; No, Hee-Cheon, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.48, pp.213 - 221, 2013-07 |
| 200816 | Thermal-hydraulic study of air-cooled passive decay heat removal system for APR plus under extended station blackout Kim, Do Yun; No, Hee Cheon; Yoon, Ho Joon; Lim, Sang Gyu, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.1, pp.60 - 72, 2019-02 |
| 200817 | Thermal-Infrared based Drivable Region Detection Yoon, Jaeshin; Park, Kibaek; Hwang, Soonmin; Kim, Namil; Choi, Yukyung; Rameau, Francois; Kweon, In So, 2016 IEEE Intelligent Vehicles Symposium, pp.978 - 985, 2016 IEEE Intelligent Vehicles Symposium, 2016-06-21 |
| 200818 | Thermal-mechanical analysis of concrete road structures under traffic load Lee, Haeng-Ki; Yang, B.J.; Na, S., The 10th World Congress on Computational Mechanics (WCCM 2012), WCCM, 2012-07-09 |
| 200819 | Thermal-Mechanical Analysis of Lead-cooled Fast Reactor Fuel Assembly with the Inverted Core Design 김형진; 류호진, 한국원자력학회 2021 온라인 추계학술발표회, 한국원자력학회, 2021-10-22 |
| 200820 | Thermal-mechanical Analysis of Lead-cooled Fast Reactor Fuel Assembly with the Inverted Core Design 김형진; 문지원; 류호진, 한국원자력학회 2023 춘계학술발표회, 한국원자력학회, 2023-05-19 |
