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33篇 您的检索式：期刊名="NuclearEngineering Design"

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	题名	作者	年代	出处	被引量
1	Current status and technical description of the Chinese 2 X 250MWth HTR-PM demonstration plant 显示文摘	ZHANG Zuoyi WU Zongxin WANG Dazhong	2009	NuclearEngineering and Design2009，239，：	1
2	Passive containment cooling by nature air convection and thermal radiation after severe accident显示文摘	Cheng X Erbacher F J Neitzel H J	2000	NuclearEngineering and Design2000，202，5：	1
3	Design of an adaptive observer-based con-troller for the water level of steam generators显示文摘	Na M G No H C	1992	NuclearEngineering and Design1992，135，3：	1
4	Phenomena-based thermal-hydraulic modelingrequirements for systems analysis of a modularhigh temperature gas-cooled reactor显示文摘	WILSON G WADSWORTH D MILLER B etal	1992	NuclearEngineering and Design1992，136，3：	1
5	PIV measurements ofturbulent jet and pool mixing produced by a steam jetdischarge in a subcooled water pool显示文摘	Yeon Jun Choo Chul-Hwa Song	2010	NuclearEngineering and Design2010，240，：	1
6	Chemo-mechanical coupling behaviour of leachedconcrete: part I experimental results 显示文摘	NGUYEN V H COLINA H TORRENTI J M	2007	NuclearEngineering and Design2007，237，2021：	1
7	CHF experiment and CFD analysisin a 2><3 rod bundle with mixing vane显示文摘	Shin B S Chang S H	2009	NuclearEngineering and Design2009，239，5：	1
8	The thermal stressanalysis and structure optimum of neck tube with verticalcryogenic insulated cylinders based on ANSYS 显示文摘	Li Yang Wang Caili Wang Rongshun	2012	NuclearEngineering and Design2012，，252：	1
9	Critical heat flux at high velocitychannel flow with high subcooling显示文摘	Sudo Y Kaminaga M	1998	NuclearEngineering Design1998，187，2：	1
10	Simulation of the fluid-structure-interaction of steam generator tubes and bluff bodies显示文摘	Kuehlert K Schowalter D Holmes W	2008	NuclearEngineering and Design2008，238，8：	1
11	Void fraction distribution in low flow rate subcooled boiling显示文摘	Edelman Z Elias E	1981	NuclearEngineering and Design1981，66，：	1
12	Correlation for the minimum in the pressure Drop versusflow-rate curves for subcooled water flowing in Narrow Heated channels显示文摘	Whittle R H Forgan R	1967	NuclearEngineering and design1967，6，：	1
13	Analytical model for time to cover cracking in RC structures due to rebar corrosion 显示文摘	Bhargava K Ghosh A K Mori Y	2006	NuclearEngineering and Design2006，236，11：	1
14	Some thermal hydraulic challen-ges in sodium cooled fast reactors 显示文摘	TENCHINE D	2010	NuclearEngineering and Design2010，240，：	1
15	Investigating the advantages and disadvantages of realistic approach and porous approach for closely packed pebbles in CFD simulation 显示文摘	WU C Y FERNG Y M CHIENG C C	2010	NuclearEngineering and Design2010，240，5：	1
16	Functional reliability analysis of safety grade decay heatremoval system of Indian 500 MWe PFBR显示文摘	Mathews T S Ramakrishnan M Parthasarathy U	2008	NuclearEngineering and Design2008，238，9：	1
17	Diffusion layer modeling ofcondensation in vertical tubes with noncondensable gases 显示文摘	Kageyama T Peterson P F Schrock V E	1993	NuclearEngineering and Design1993，141，：	1
18	Ex-vessel boiling experiments : Laboratory- andreactor-scale testing of the flooded cavity conceptfor in-vessel core retention, Part II : Reactor-scale boiling experiments of the flooded cavityconcept for in-vessel core retention 显示文摘	CHU T Y BENTZ J H SLEZASEDAG S E	1997	NuclearEngineering and Design1997，169，：	1
19	The design features of the HTR-10显示文摘	WU Zongxin LIN Dengcai ZHONG Daxin	2002	NuclearEngineering and Design2002，218，：	1
20	An experimental investigation of apassive cooling unit for nuclear plant containment 显示文摘	Liu H Todreas N E Driscoll M J	2000	NuclearEngineering and Design2000，199，：	1

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