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3679篇 您的检索式:期刊名="Nuclear Engineering Design"
    题名 作者 年代 出处 被引量
1Study on steel plate reinforced concrete panels subjected to cyclic in-plane shear显示文摘Masahiko Ozaki Shodo Akita Hiroshi Osuga Tatsuo Nakayama Naoyuki Adachi 2003Nuclear Engineering and Design2003,,1:3
2Early-age behaviour of concrete nuclear containments显示文摘F. Benboudjema J.M. Torrenti 2008Nuclear Engineering and Design2008,,10:2
3Seismic behaviour and design of steel coupling beams in a hybrid coupled shear wall systems显示文摘Wan-Shin Park Hyun-Do Yun 2006Nuclear Engineering and Design2006,,23:2
4Seismic proof test of a reinforced concrete containment vessel (RCCV)显示文摘Toshihiko Hirama Masashi Goto Keiji Shiba Toshio Kobayashi Ryozo Tanaka Shizuo Tsurumaki Katsuki Takiguchi Hiroshi Akiyama 2005Nuclear Engineering and Design2005,,13:2
5Study on two-phase flow dynamics in steam injector 显示文摘Narabayashi T Mizumach W Mori M 1997Nuclear Engineering and Design1997,175,12:2
6The Effect of Flow Direction on CHF for Low Pressure Water in Thin Rectangular Channel 显示文摘Mishima K Nishihara H 1985Nuclear Engineering and Design1985,86,:2
7Current status and technical description of Chinese 2<ce:hsp sp='0.25'/>×<ce:hsp sp='0.25'/>250<ce:hsp sp='0.25'/>MW th HTR-PM demonstration plant显示文摘Zuoyi Zhang Zongxin Wu Dazhong Wang Yuanhui Xu Yuliang Sun Fu Li Yujie Dong 2009Nuclear Engineering and Design2009,,7:2
8Finite element formulation and solution of nonlinear heat transfer显示文摘Bathe K J Khoshgoftaar M R 1979Nuclear Engineering and Design1979,51,:2
9Study on a concrete filled structure for nuclear power plants显示文摘M. Takeuchi M. Narikawa I. Matsuo K. Hara S. Usami 1998Nuclear Engineering and Design1998,,2:2
10Analytical studies on local damage to reinforce concrete structures under impact loading by discrete element method显示文摘Sawamoto Y Tsubota H Kasai Y 1998Nuclear Engineering and Design1998,179,:1
11Determination of two-phase interracial areas by an ultrasonic technique 显示文摘Chang J S Morala E C 1990Nuclear Engineering and Design1990,122,:1
12Investigation of waterhammer in piping networks with voids containing non- condensable gas显示文摘Lai A Hau K F Swartz R 2000Nuclear Engineering and Design2000,,197:1
13Small-break loss-of-coolant accident analysis for pressurized water reactors with an advanced drift-flux model in ATHLET显示文摘KIRMSE R POINTNER W SONNENBURG H G 1995Nuclear Engineering and Design1995,154,1:1
14Scientific Paradigms of Structural Safety of Aged Plants--Lessons Learned from Russian activities显示文摘Saji Genn Timofeev Boris 2009Nuclear Engineering and Design2009,239,:1
15Analytical model for time to covet cracking in RC structures due to rebar corrosion显示文摘BHARGAVA K GHOSH A K MORI Y 2006Nuclear Engineering and Design2006,,236:1
16On the Analogies in the Dynamic Behav- ior of Heated Channels with Boiling and Supereritical Fluids显示文摘Ambrosini W 2007Nuclear Engineering and Design2007,237,:1
17Applications of large eddy simulations in nuclear field显示文摘SIMONEAU J P CHAMPIGNY J GELINEAU O 2010Nuclear Engineering and Design2010,240,2:1
18Experimental study of heat transfer enhancement in narrow rectangular channel with longitudinal vortex generators 显示文摘WANG Qiu-wang CHEN Qiu-yang WANG Ling 2007Nuclear Engineering and Design2007,237,:1
19Rocking response of tanks containing two liquids 显示文摘TANG Y 1994Nuclear Engineering and Design1994,152,13:1
20The GO-FLOW reliability analysis methodology-analysis of common cause failures with uncertainty显示文摘Matasuoka Takeshi Kobayashi Michiyuki 1997Nuclear Engineering and Design1997,175,3:1
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