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	题名	作者	年代	出处	被引量
1	Solvent Extraction Study of 233Pa(Ⅴ) With 1-phenyl-3-methyl-4-benzoyl-5-pyrazolone显示文摘	DING Huajie NIU Yanning YANG Weifan	2005	J Nucl Sci Tech2005，42，：	1
2	Derivation ofan equation for ra dionuclide transport in porous media显示文摘	CHEN F L LI S H	1990	Nucl Tech nol1990，90，1：	1
3	Simulation of the Inhibition of Waterα-Radiolysis via H2Addition显示文摘	LERTNAISAT P KATSUMURA Y MUKAI S	2014	J Nucl Sci&Tech2014，51，9：	1
4	MCMG: a 3-D multigroup P3 Monte Carlo code and its benchmarks显示文摘	Deng Li Xie Zhongsheng Zhang Jianming	2001	J Nucl Sci Tech2001，37，7：	1
5	MCMG:A 3-D multigroup Monte Carlo code and its benchmarks显示文摘	Dang Li Xie Zhongsbeng Zhang Jianming	2000	J Nucl Sci Tech2000，37，7：	1
6	Nuclear Fuel Management Optimization Using Genetic Algotithms显示文摘	Dechaine M D Feltus M A	1995	Nucl Tech1995，111，：	1
7	A Study on Preparation of ^188W-^188Re Generator显示文摘	YIN DZ HU WQ CAI XM	1998	Nucl Tech1998，21，1：	1
8	ATWS Characteristics of Super LWR with/without Alternative Action 显示文摘	Ishiwatari Y Oka Y Koshizuka S	2007	Nucl Sci and Tech2007，44，4：	1
9	Limits of nuclear coordinates for stable region显示文摘	WANG YuYing	1995	Nucl Sci and tech1995，32，2：	1
10	Forced convection heat transfer and temperature fluctuations of lithium under transverse magnetic fields显示文摘	Uda N Miyazawa A Inoue S	2001	J Nucl Sci and Tech2001，38，11：	1
11	A Monte Carlo Model for Gamma-Ray KleinNishina Scattering Probabilities to Finite Detectors 显示文摘		1996	J of Nucl Sci Tech1996，33，9：	1
12	New scanning- power supply of Dynamitron accelerator显示文摘	GONG Peirong LU Songlin SI Houzhi	1999	Nucl Tech1999，22，1：	1
13	3-D neutron transport benchmark显示文摘	Takeda T Ikeda H	1991	Journal of Nucl Sci Tech1991，28，7：	1
14	MCMG : A 3 D multigroup Monte-Carlo code and its benchmarks显示文摘	DENG Li XIE Zhongsheng ZHANG Jianming	2000	J Nucl Sci Tech2000，37，7：	1
15	Basic properties of a zirconia-based fuel material for light water reactors显示文摘	Degueldre Paratte J M	1998	Nucl Tech1998，123，1：	1
16	Measurements of thoron concentration by passive cup method and its application to dose assessment显示文摘	GUO Q J IIDA T OKAMOTO K	1995	J Nucl Sci Tech1995，32，8：	1
17	Development of Mixed-oxide Fuel Manufacture in the United Kingdom and the Influence of Fuel Characteristics on Irradiation Performance显示文摘	Macleod HM Yates G	1993	Nucl Tech1993，102，：	1
18	Critical heat flux enhancement using local tangential flow injection显示文摘	DHIR V K	1983	Nucl Tech/Fusion1983，4，：	1
19	In-pile Performance of Mixed-oxide Fuel With Particular Emphasis on MIMAS Fuel显示文摘	Deramaix D Haas D van de Veldt J	1993	Nucl Tech1993，102，：	1
20	A study on mutagenic effects of antibiotic-producers by ion implantation显示文摘	Xie L Q Zhang Y F Chen R Y ct al	1995	Nucl Tech1995，18，6：	1

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