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三种方法求解药物溶出度Weibull分布参数的探讨 被引量:9
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作者 郭剑伟 吴俊珠 +3 位作者 王成军 高鹏飞 缪菊莲 杨志勇 《大理学院学报(综合版)》 CAS 2011年第8期1-4,共4页
目的:探讨3种方法求算药物溶出度Weibull分布参数的结果差别。方法:分别采用计算器、EXCEL和SPSS软件处理药物溶出数据。结果:3种方法计算得到的T50、Td值和Weibull分布参数m值很接近,但参数г和t0间相差较大。结论:药物溶出度Weibull... 目的:探讨3种方法求算药物溶出度Weibull分布参数的结果差别。方法:分别采用计算器、EXCEL和SPSS软件处理药物溶出数据。结果:3种方法计算得到的T50、Td值和Weibull分布参数m值很接近,但参数г和t0间相差较大。结论:药物溶出度Weibull分布参数的计算结果在准确度上SPSS法>EXCEL法>计算器法。 展开更多
关键词 药物溶出度 WEIBULL分布 统计计算器 EXCEL SPSS
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An efficient authentication scheme based on one-way key chain for sensor network
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作者 郎为民 程文青 杨宗凯 《Journal of Harbin Institute of Technology(New Series)》 EI CAS 2007年第6期756-760,共5页
To strike a tradeoff between the security and the consumption of energy,computing and communication resources in the nodes,this paper presents an efficient authentication scheme based on one-way key chain for sensor n... To strike a tradeoff between the security and the consumption of energy,computing and communication resources in the nodes,this paper presents an efficient authentication scheme based on one-way key chain for sensor network. The scheme can provide immediate authentication to fulfill the latency and the storage requirements and defends against various attacks such as replay,impersonation and denial of service. Meanwhile,our scheme possesses low overhead and scalability to large networks. Furthermore,the simple related protocols or algorithms in the scheme and inexpensive public-key operation required in view of resource-starved sensor nodes minimize the storage,computation and communication overhead,and improve the efficiency of our scheme. In addition,the proposed scheme also supports source authentication without precluding in-network processing and passive participation. 展开更多
关键词 system design sensor network AUTHENTICATION key establishment passive participation
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Neutron Radiography System Collimator Design via Monte Carlo Calculation
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作者 H. Jafari M. Shahriari 《Journal of Energy and Power Engineering》 2011年第12期1168-1172,共5页
Neutron radiography uses the unique interaction probabilities of neutrons to create images of materials. This imaging technique is non-destructive. MCNP Monte Carlo Code has been used to design an optimized neutron ra... Neutron radiography uses the unique interaction probabilities of neutrons to create images of materials. This imaging technique is non-destructive. MCNP Monte Carlo Code has been used to design an optimized neutron radiography system that utilizes 241Am-Be neutron source. Many different arrangements have been simulated to obtain a neutron flux with higher amplitude and more uniform distribution in the collimator outlet, next to image plane. In the final arrangement the specifications of neutron filter, Gamma-ray shield and beam collimator has been determined. Simulations has been carried out for a 5Ci 241Am-Be neutron source. In this case 43.8 n/cm2s thermal neutron flux has been achieved at a distance of 35 cm from neutron source. 展开更多
关键词 241Am-Be radioisotope source neutron radiography Monte Carlo collimator.
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