loca

Finally , numerical simulation demonstrated the different effects of different algorithm parameters on the loca of particle position and particle velocity , and further illustrated the validity of conclusions given in this paper .

数值仿真实验展示了不同子区域内的算法参数对粒子位置和粒子速度运动轨迹的不同影响，进一步验证了所得结论的正确性。

The loca of their thought accorded with the essential prescript to individual cultural accomplishment and the releasing discipline of Chinese cultural tradition 's mighty vitality , and also it tallied with great masters ' individuation character .

他们思想的演进轨迹完全符合个人知识文化素养的本质规定性，完全符合源远流长、博大精深的中国文化传统强大生命力的释放规律，完全符合思想大家的个性化特征。

Research on Reactor Dynamic Analysis under Seismic and LOCA Conditions

核反应堆地震和失水事故下结构动力分析研究

Nonlinear Dynamic Analysis under LOCA Condition for Reactor System

反应堆系统LOCA非线性动力分析

Simulation of LOCA in the auxiliary primary loop system of nuclear power plant

核动力装置一回路辅助系统失水事故的仿真研究

Experiment study on small break LOCA of nuclear heating reactor

核供热堆小破口事故实验研究

Verification of Licensing LOCA Analysis Program and Three-Dimension Effect Study

认证级LOCA分析程序验证及其三维效应的研究

Dynamic Response Analysis for Fuel Assemblies under Earthquake and LOCA Accidents

燃料组件在地震和失水工况下的结构动力反应分析

Loca stress analysis of anchorage zone saddle of part cable-stayed bridge

部分斜拉桥鞍座锚固区局部应力分析

The analysis and checking calculation of LOCA simulating test in an advanced thermal reactor

新型转换堆失水事故模拟实验的验算和分析

Structural Response Research for Primary Components under Earthquake and LOCA Accidents on NPP

核电厂主设备在地震加失水事故下的结构反应分析研究

Blowdown Force During the Large LOCA for 600 MW Nuclear Power Plant

60万千瓦核电站大破口失水事故中的喷射力

The application of trac-pf1 to the analysis of large break loca

TRAC-PF1在大破口LOCA分析中的应用

The Linear Dynamic Response Analysis on a Core Barrel under the LOCA Condition in Primary Piping

主管道失水事故时吊篮动态响应线性分析

Instability under flow break by nuclear heating reactor LOCA

核供热堆失水自然循环断流时的流动不稳定性

Simulation Experiment of Small Break LOCA in Upper Plenum

上空腔小破口失水事故模拟实验

The influence of break area on transient thermohydraulic characteristics of a small break loca

破口面积对小破口失水事故瞬态热工水力特性的影响

Operator Reliability Analysis during NPP Small Break LOCA

小破口失水事故处理中人员的行为可靠性分析

Introduction of DRM for Large Break LOCA Analysis

大破口失水事故的DRM分析方法介绍

Licensing LOCA analysis is an important issue of Nuclear Power Plant ( NPP ) design and safety analysis .

认证级LOCA分析是核电厂设计和安全分析的重要内容之一。

Transient thermohydraulic characteristics under blowdown conditions simulating a small break loca

小破口失水事故喷放阶段瞬态热工水力特性的模拟试验研究

Experimental investigation on transient critical heat flux under low pressure blowdown conditions simulating a small break loca

模拟小破口低压喷放失水工况下瞬态CHF实验研究&均匀加热垂直圆管实验

Grub and Loca Gyrus Grasping Rock Machine Matching Use in the Alluvium Construction

立井冲积层施工中挖掘机与中心回转抓岩机的配套使用

The details of dynamic response analysis for reactor and steam generator under LOCA and seismic loading were performed .

对堆本体和蒸汽发生器在失水事故和地震载荷下的动态响应作了详细的分析。

Experiment result is significant for safe operation of nuclear heating reactor and security analysis program to confirm small break LOCA .

实验结果对核供热堆的安全运行及验证小破口事故安全分析程序有重要意义。

The characteristics of large break loss of coolant accident ( LOCA ) for Xi'an Pulsed Reactor were analyzed .

失水事故是核电站设计的基准事故之一，是压水堆事故分析关注的重点。

It is necessary to determine switchover time to simultaneous cold and hot leg safety injection during LOCA long-term core cooling .

在失水事故长期冷却过程中，必须确定安全注射系统从冷段注射切换到冷热段同时注射的切换时间。

Experimental research of heat transfer on vertical nonuniformly cosine heated tube with simulated loca blowdown condition of PWR

非均匀余弦加热垂直圆管在模拟压水堆失水事故喷放工况下的传热研究

GNPS 18-Months Fuel Cycles Non - LOCA Accident Analyses

大亚湾核电站18个月换料非失水事故分析

Analysis of Small Break LOCA for ACR-700 NPP

ACR-700核电厂小破口失水事故分析