| 8861 | THERMAL POWER PREDICTION OF NUCLEAR-POWER-PLANT USING NEURAL NETWORK AND PARITY SPACE MODEL ROH, MS; CHEON, SW; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.38, no.2, pp.866 - 872, 1991-04 |
| 8862 | Thermal Property Simulation of ZrO2-based Nanocomposites for Inert Matrix Fuel Vivek Raj; Mistarihi, Qusai; 류호진, 한국원자력학회 2015 춘계학술대회, 한국원자력학회, 2015-05-07 |
| 8863 | Thermal-hydraulic analysis and design of printed circuit heat exchangers for KAIST Advanced Pyro-SFRs = KAIST Advanced Pyro-SFRs의 인쇄기판형 열교환기의 열수력적 분석 및 설계link Kang, Gil-Beom; 강길범; et al, 한국과학기술원, 2013 |
| 8864 | 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 |
| 8865 | 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 |
| 8866 | 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 |
| 8867 | Thermal-hydraulic Analysis of the GT-MHR Core using Axiomatic Design Jeong, HD; Chang, Soon-Heung, NUTHOS-7, 2008-10-05 |
| 8868 | 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 |
| 8869 | 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 |
| 8870 | Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop No, Hee Cheon, the KNS Autumn Meeting |
| 8871 | 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 |
| 8872 | 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 |
| 8873 | Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs 노희천; 전병국, KNS Spring, KNS Spring, 2014-05-29 |
| 8874 | 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 |
| 8875 | Thermal-hydraulic experiments for the PCHE type steam generator 노희천; 신창욱, KNS Spring, KNS Spring, 2015-05-07 |
| 8876 | 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 |
| 8877 | Thermal-Hydraulic Performance Tests of PCHE Using Mixture-Gas for HTGRs No Hee Cheon; Kim, In Hun, American Nuclear Society, 2011-06 |
| 8878 | 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 |
| 8879 | 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 |
| 8880 | 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 |
