| 4821 | Thermal Hydraulic Design Parameters Study for Severe Accidents Using Neural Network Roh, CH; Chang, KS; Chang, Soon-Heung, The 6th International Conference on Nuclear Engineering, 1998 |
| 4822 | Thermal Hydraulic Performance of the Printed Circuit Heat Exchanger in a Helium Test Loop No, Hee Cheon, Nthas6 2008 |
| 4823 | Thermal hydraulic-Mechanic Integrated Simulation for Advanced Cladding Thermal Shock Fracture Analysis during Reflood Phase in LBLOCA Son, Seongmin; Lee, Youho; Cho, Jaewan; Lee, Jeong-Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05-12 |
| 4824 | Thermal loading perspective on U.S. nuclear waste repository needs Stahala, Mike P.; Yim Man-Sung; McNelis, David N., 2006 Annual Meeting - American Nuclear Society, v.94, no.2006, pp.329 - 330, Transactions of the American Nuclear Society, 2006-06 |
| 4825 | Thermal Loading Perspective on U.S. Nuclear Waste Repository Needs Mike Stahala; Yim Man-Sung; David McNelis, Transactions of the American Nuclear Society, v.94, no.2006, pp.329 - 330, American Nuclear Society, 2006-06 |
| 4826 | Thermal Performance Evaluation of Spent Fuel Pool Cooling System with Water Jacket and Heat Pipe 이상훈; 이민석; 박우성; 정용훈, 2023 한국원자력학회 춘계학술발표회, 한국원자력학회, 2023-05-18 |
| 4827 | Thermal Performance Test through On-line Turbine Cycle Performance Monitoring in Nuclear Power Plants Heo, GY; Lee, SJ; Choi, SS; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 1999 |
| 4828 | Thermal Power Estimation Using De-noising and an Autoassociative Neural Network in Nuclear Power Plant Heo, GY; Choi, SS; Chang, Soon-Heung, '98 ANS Winter Meeting, ANS, 1998 |
| 4829 | Thermal Property Simulation of ZrO2-based Nanocomposites for Inert Matrix Fuel Vivek Raj; Mistarihi, Qusai; 류호진, 한국원자력학회 2015 춘계학술대회, 한국원자력학회, 2015-05-07 |
| 4830 | 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 |
| 4831 | Thermal-hydraulic Analysis of the GT-MHR Core using Axiomatic Design Jeong, HD; Chang, Soon-Heung, NUTHOS-7, 2008-10-05 |
| 4832 | 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 |
| 4833 | 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 |
| 4834 | Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop No, Hee Cheon, the KNS Autumn Meeting |
| 4835 | Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs 노희천; 전병국, KNS Spring, KNS Spring, 2014-05-29 |
| 4836 | Thermal-hydraulic experiments for the PCHE type steam generator 노희천; 신창욱, KNS Spring, KNS Spring, 2015-05-07 |
| 4837 | Thermal-Hydraulic Performance Tests of PCHE Using Mixture-Gas for HTGRs No Hee Cheon; Kim, In Hun, American Nuclear Society, 2011-06 |
| 4838 | 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 |
| 4839 | 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 |
| 4840 | Thermal-sizing of the molten salt reactor system with gas Brayton cycle 손인우; 최성욱; 김상지; 이정익, 2021 한국원자력학회 추계학술발표회, 한국원자력학회, 2021-10-21 |
