期刊文献+
共找到2篇文章
< 1 >
每页显示 20 50 100
Bearing Capacity of Mixed Pile with Stiffness Core 被引量:3
1
作者 岳建伟 姜忻良 凌光荣 《Transactions of Tianjin University》 EI CAS 2006年第3期204-208,共5页
To study load transfer mechanism and bearing capacity of a mixed pile with stiffness core (MPSC), which is formed by inserting a precast reinforced concrete pile (PRCP), in-situ tests involving MPSCs with differen... To study load transfer mechanism and bearing capacity of a mixed pile with stiffness core (MPSC), which is formed by inserting a precast reinforced concrete pile (PRCP), in-situ tests involving MPSCs with different lengths, diameters, water cement ratios and PRCPs, cement mixed piles, and drilling hole piles, were carried out. Limit bearing capacities, load-settlement curves and stress distribution of MPSCs and mixed piles were obtained. The load transfer between cement soil and PRCP was analyzed by finite element method (FEM). Test results and FEM analysis show that an MPSC has fully utilized the big friction from a cement mixed pile and the high compressive strength from a PRCP which transfers outer top load into the inner cement soil, and that inserting a PRCP into a mixed pile changes the stress distribution of a mixed pile and improves frictional resistance between a mixed pile and soil. The length and the section area on PRCP of an MPSC both have an optimum value. Adopting MPSC is effective in improving the bearing capacity of soft soil ground. 展开更多
关键词 mixed pile mixed pile with stiffness core (MPSC) pressing soil effect
在线阅读 下载PDF
SCWR for Future Large-Scale Nuclear Power Generation
2
作者 Cheng Xu 《工程科学(英文版)》 2007年第4期68-75,共8页
The ambitious nuclear power program motivates the Chinese nuclear community to develop advanced reactor concepts of generation IV,in order to ensure the long-term,stable and sustainable development of nuclear power.Th... The ambitious nuclear power program motivates the Chinese nuclear community to develop advanced reactor concepts of generation IV,in order to ensure the long-term,stable and sustainable development of nuclear power.The supercritical water-cooled reactor(SCWR)has favorable features in economics,sustainability and technology availability.It is the logical extension of the existing PWR technology and has very promising perspectives in large-scale power generation in China.This paper describes the main features of SCWR.New designs of SCWR core structure and fuel assemblies are proposed.Preliminary analysis using a coupled neutron-physics/thermal-hydraulics method is carried out and shows a good feasibility of the new design proposal. 展开更多
关键词 supercritical water cooled reactor mixed core coupled method
在线阅读 下载PDF
上一页 1 下一页 到第
使用帮助 返回顶部