Handbook of Nuclear Engineering: Vol. 1: Nuclear Engineering Fundamentals; Vol. 2: Nuclear Reactor Analysis; Vol. 3: Nuclear Power Reactors; Vol 4: Experimental Reactors and Nuclear Fuel Cycles, 4.
核工程手册：第一卷。1：核工程基础；成交量。2：核反应堆分析；成交量。3：核电反应堆；成交量4：实验反应堆和核燃料循环。
We're gonna look at both infinite reactor systems and finite reactor systems to identify the differences, certainly in analysis.
我们会观察无限反应堆系统，以及有限反应堆系统，得出它们的区别，当然是在分析中。
When most people do an analysis the likely number of groups could be like thirty or so to properly capture what might be going on in a reactor.
当大多数的人作分析的时候,群的数目可能是30左右,这样能正确的捕获在一个反应堆里发生的。
Considering the critical components like reactor coolant lines and oil-well casings, the metal parts are subjected to prior replacement, for safety, with respect to a worst-case analysis of failure.
考虑到关键部件如反应堆冷却剂线和油井涂层不能出现问题，为了安全，并对失效做了最坏的分析，这类金属零件会得到优先更换。
Analysis of fuel assembly is an important step in reactor physics design.
组件计算是堆物理计算中的一个重要环节。
Perturbation calculation will be required to rapidly determine the changes of reactivity caused by core neutron cross sections perturbation in reactor physics design and analysis.
在反应堆物理设计和分析时，经常要进行微扰计算，以快速分析堆芯中子截面扰动下反应性的变化量。
Parameter estimation in dynamical systems, example : least squares fitting of rate constants from batch reactor data, parametric sensitivity analysis.
动态系统之参数估算，范例：利用批式反应器数据做速率常数之最小平方配适，参数灵敏度分析。
In this thesis, stress analysis and calculation for a large oxidized reactor considering are made by using ANSYS FEM code.
本课题用ANSYS软件对某大型氧化反应器流固耦合进行了有限元应力分析计算。
Test Blanket Module (TBM) is a key component of the International Thermonuclear Experi-mental Reactor (ITER). Its design involves multi-disciplinary optimization analysis.
试验包层模块(TBM)是国际热核聚变实验堆(ITER)的关键核心组件，其设计涉及多学科综合优化分析。
The geometric buckling is of great value in application to criticality problem and analysis of dynamic process of supercritical system in fast fission reactor.
在快裂变反应堆的临界问题和超临界系统动力学过程的分析中，几何曲率有重要的应用价值。
Real Programmers don't write in FORTRAN. FORTRAN is for wimpy engineers who wear white socks. The get excited over finite state analysis and nuclear reactor simulations.
真正的程序员不写fortran程序。fortran是让畏缩的白领工程师用的。那些人只钟情于有限的状态分析和核反应堆模拟。
After having completed the model analysis of the pressurized water reactor (PWR) core barrel in an 1:10 model, the dynamic characteristics are obtained.
在反应堆1：10模型上进行了堆芯吊篮结构的空气和静水中模态分析试验，获得动态特性。
The finite element method is applied to analysis and optimize the design of the hydrogenation reactor skirt support area, and stress of the risk section is assessed and strength is checked.
采用有限元法对加氢反应器裙座支撑区进行有限元分析及优化设计，并对其危险截面作应力评定和强度校核。
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 improved transient sealing analysis program for reactor pressure vessel is applied to analyze the 1/4 structure of the model under the cool and the thermal work conditions.
应用改进后的反应堆压力容器瞬态密封分析程序对压力容器模拟体1/4模型进行了冷态和热态密封分析。
An automatic data processing system for reactor neutron activation analysis is designed for personal computer in DOS environment.
介绍了一个在微机上建立的反应堆中子活化分析数据自动处理系统。
The fast reactor safety analysis is the foundation and key of FBR research work.
快堆安全分析是快堆研究工作的基础和重点。
After having completed the model analysis of the pressurized water reactor (PWR) core barrel in anl: 10 model, the dynamic characteristics are obtained.
在反应堆1：10模型上进行了堆芯吊篮结构的空气和静水中模态分析试验，获得动态特性。
Reasons of failure in cooling pipe of the reactor have been studied by the chemical composition analysis, optical microscopy examination and electron probe microanalysis.
应用化学分析、金相和电子探针显微分析技术对反应器中冷却水管的失效原因进行了分析。
Based on an exact mathematic model, a measurement method regarding core thermal power of nuclear power pressurized water reactor and its error analysis were presented in this paper.
通过建立精确的数学模型，提出了一种测量核电站压水反应堆堆芯热功率的方法，并对该方法进行了误差分析。
Real Programmers don't write in FORTRAN. FORTRAN is for wimpy engineers who wear white socks. The get excited over finite state analysis and nuclear reactor simulations.
真正的程序员不用FORTRAN，FORTRAN是给穿白袜子的幼稚工程师们用的。他们热衷于有限元分析和核反应模拟。
The analysis of long term cooling for a pool type reactor after shutdown is presented.
对一座池式反应堆剩余发热长期冷却进行了分析。
In this thesis, finite element analysis is carried out on a large polypropylene tubular loop reactor which is complicated both in structure and loadings.
本文对结构和受载都非常复杂的聚丙烯环管反应器建立了有限元分析设计模型。
Two phase countercurrent flow in reactor hot leg at loss of coolant accident is studied by experiment and analysis.
对反应堆失水事故条件下热管段内的两相流逆向流动过程进行了实验研究和理论分析。
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。
An introduction is given to technological flow, parameters, and control of membrane contamination of the biological reactor, and analysis was made of its mechanism and characteristics.
通过膜生物反应器在铁路单位生活污水处理的实例，对其工艺流程、运行参数、膜污染的控制进行介绍，分析其机理和特点。
This paper presents a comprehensive analysis to the safety of the overheated SB46 reactor and indicates that the reactor can be used with safety continuously.
本文对超温后的SB46反应器进行了全面的安全分析，指出该反应器能够继续安全使用。
Based on mechanism analysis, a dynamic model of FCCU reactor-regenerator system is given. It can be used for simple process characteristic analysis and for control system simulation.
针对催化裂化装置反应再生系统，进行了动态机理建模研究，给出了可以用于过程特性分析和控制系统仿真研究的动态机理模型。
They are the natural circulation flow analysis code (MC-FLOW), the core thermal hydraulic analysis code (MC-THAS) and the pulsed reactor transient analysis code (MC-TRAN).
它包括脉冲堆自然循环分析程序（MC-FLOW）、堆芯热工水力分析程序（MC-THAS）和脉冲堆瞬态分析程序（MC-TRAN）。
Based on the motion equation and flow circulation in the system, the flow analysis to reactor coolant system with density locks is given; the action and characteristics of density locks are explained.
对安装有密度锁的反应堆冷却剂系统进行了流动分析，根据流体运动方程和系统的循环流动特性，说明了密度锁的作用和具有的特性。
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