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84篇 您的检索式：期刊名="Nuclear Engineering Technology"

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	题名	作者	年代	出处	被引量
1	Neutronics Performance Evaluation of Fast-Fission Fuel Breeding Blankets for a Fusion-Fission Hybrid Reactor显示文摘	WANG Minghuang JIANG Jieqiong LIU Jinchao	2009	9th International Symposium on Fusion Nuclear Technology Dalian China Fusion Engineering and Design2009，2009，：	1
2	Human-machine interaction in Nuclear power plant显示文摘	H Yoshikawa	2005	Nuclear Engineering and Technology2005，37，2：	1
3	Assessment of CFD Codes used in nuclear reactor safety simulations显示文摘	Smith Brian L	2010	Nuclear Engineering and Technology2010，42，4：	1
4	A mixed core for supercritieal water-cooled reactors 显示文摘	Cheng X Liu X J Yang Y H	2008	Nuclear Engineering and Technology2008，40，2：	1
5	Critical Heat Flux for Downward-Facing Boiling on A Coated Hemispherical Vessel Surrounded by an Insulation Structure 显示文摘	Yang J Cheung F B Rempe J L	2006	Nuclear Engineering and Technology2006，38，2：	1
6	A mixed core for supercritical water-cooled reactors 显示文摘	CHENG X LIU X J YANG Y H	2008	Nuclear Engineering and Technology2008，40，2：	1
7	A mixed core for supercritical water-cooled reactors 显示文摘	CHENG Xu LIU Xiao-jing YANG Yan-hua	2007	Nuclear Engineering and Technology2007，40，2：	1
8	Corrosion behavior of austenitie and ferritie steels in supercritical water 显示文摘	Luo X Tang R Long C S	2008	Nuclear Engineering and Technology2008，40，2：	1
9	A mixed core for supercritical water-cooled reactors 显示文摘	CHENG X LIU X J YANG Y H	2008	Nuclear Engineering and Technology2008，40，2：	1
10	Issues in probabilistic seismic hazard analysis for nuclear facilities in the US 显示文摘	Robin K M	2009	Nuclear Engineering and Technology2009，41，10：	1
11	Critical flow experiment and analysis for su- percritical fluid显示文摘	MIGNOT G ANDERSON M CORRADINI M L	2007	Nuclear Engineering and Technology2007，40，2：	1
12	Development of a vulnerability assessment code for a physical protec- tion system: Systematic Analysis of Physical Protection (SAPE) 显示文摘	Jang S Kwak S W O O Yoo H	2009	Nuclear Engineering and Technology2009，5，：	1
13	Challenges and prospects for whole-core Monte Carlo analysis 显示文摘	MARTIN W	2012	Nuclear Engineering and Technology2012，44，2：	1
14	Identification and evaluation of human factors issues associated with emerging nucle- ar plant technology显示文摘	O'Hara J M Higgins J C Brown W	2009	Nuclear Engineering and Technology2009，41，3：	1
15	A mixed core for supercritical water-cooled reactors 显示文摘	Cheng X Liu X Yang Y	2008	Nuclear Engineering and Technology2008，40，2：	1
16	Assessment of Gas Cooled Fast Reactor with lndirect Supercritical CO2 Cycle显示文摘	Hejzlar P Dostai V Driscoll M J	2006	Nuclear Engineering and Technology(Special Issue on 1CAPP 05)2006，38，2：	1
17	Monte Carlo method extended to heat transfer problems with non-constant temperature and convection boundary conditions显示文摘	Cho B H Cho N Z	2010	Nuclear Engineering and Technology2010，42，1：	1
18	Simulated AP1000 response to design basis small-break LOCA events in APEX- 1000 test facility 显示文摘	WRIGHT R F	2007	Nuclear Engineering and Technology2007，39，4：	1
19	Fundamentals and Recent Developments of Reactor Physics Methods显示文摘	Nam Zin Cho	2005	Nuclear Engineering and Technology2005，37，1：	1
20	A practical look at Monte Carlo variance reduction methods in radiation shielding 显示文摘	Olsher R H	2006	Nuclear Engineering and Technology2006，38，4：	1

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