研究堆

研究堆燃料的~（235）U富集度对材料核发热的影响

The Effect of Nuclear Heating on Material With Different Enrichment of ~ ( 235 ) U in Research Reactor

中国先进研究堆（CARR）回路系统总体设计特点

Design Characteristics of China Advanced Research Reactor ( CARR ) Loops

研究堆水系统电气设备与过程控制（DCS）系统接口串扰现象的分析

Analysis Crosstalk the Interface between Water Electric Equipment and DCS System

研究堆乏燃料组件中~（235）U含量和燃耗的测定

Measurement of ~ ( 235 ) U Mass and Burnup in Fuel Assembly in Research Reactors

中国先进研究堆（CARR）工程燃料组件设计验证试验

Design Validation Test of Fuel Assembly of China Advanced Research Reactor

在德黑兰大学，政府正在美国的帮助下建造一座核研究堆，这是艾森豪威尔（Eisenhower）总统原子能为和平服务（AtomsforPeace）计划的一部分。

At the University of Tehran , the government was building a nuclear research reactor with US assistance through Eisenhower 's Atoms for Peace programme .

中国先进研究堆（CARR）上的中子散射工程

Neutron scattering project on CARR

堆芯容器及堆内构件是中国先进研究堆（CARR）中的关键设备之一。

The core vessel and core structure of China Advanced Research Reactor ( CARR ) are one of the key components .

简要介绍了国际原子能机构（IAEA）近年来在研究堆开发与安全管理方面的重要举措，以及未来发展的趋势。

This paper presents the recent activities of IAEA on the research reactor safety , and the trends in the future .

针对国内目前研究堆的现状，建议与IAEA开展相关合作。

According to the present situation of national research reactors , some suggestions are proposed for the cooperation with IAEA on research reactor safety .

10MW高温气冷实验堆（HTR-10）属于研究堆类型，但又具有小型核动力堆的运行模式；

MW high temperature gas-cooled reactor ( HTR-10 ) has both features of research re-actors and operation model of power plants .

基于物理启动、同位素生产以及空间燃耗不同考虑的全堆芯模型，采用少群扩散方法对中国先进研究堆（CARR）堆芯进行计算。

The neutronics analysis of China Advanced Research Reactor is carried out with the diffusion method by using the whole core module in this paper .

介绍了中国先进研究堆（CARR）水平孔道的用途、在堆本体的布置、水平孔道结构设计及设计方面的特点。

This paper introduces the applications of the horizontal channels in CARR and their arrangement in the reactor complex , structure design and design characteristics .

本工作针对中国先进研究堆（CARR）的堆工程需要，研制开发了CITA&TOOL接口管理软件。

CITA - TOOL , a nuclear parameters management interface code needed by China advanced research reactor ( CARR ) physics analysis , is presented .

这些设计特点，体现了CARR设计的先进性、安全性、经济性和创新性，是我国研究堆设计水平的具体体现。

These distinguishing features reflected the advanced merit , safety performance , economics and innovatives of CARR and the present level of research reactor design in China .

中国先进研究堆ATWS事故缓解系统设计改进安全分析

Safety Analysis of ATWS Accident Mitigating System Improving Design for China Advanced Research Reactor

中国先进研究堆（CARR）是一座可为我国核科学研究提供重要科学研究平台的高技术性能、多用途的反应堆。

China advanced research reactor ( CARR ) is a high performance and multipurpose reactor which provide important science research platform for our country 's nuclear scientific research .

应用计算流体力学软件CFX，采用多孔介质模型对中国先进研究堆（CARR）的堆芯流量分配进行了数值模拟。

Using CFX , the numerical simulation of the core flow distribution was performed for China Advanced Research Reactor ( CARR ) with the porous media model .

考虑辐射安全和经济性，对中国先进研究堆（CARR）的水平烫源孔道作了屏蔽设计优化研究。

Considering the radiation security and economy factors , optimization study is done on the shielding design for the horizontal heat source ducts of China advanced research reactor ( CARR ) .

本文着重就中国先进研究堆（CARR）设计文件管理体系的建立、文件管理制度的制定以及对各类设计文件管理的实施等方面进行了阐述。

This paper briefs on the establishment of document management system , the formulation of document management regulations , and the implementation of management measures for various documents in CARR engineering design .

冷中子源是中国先进研究堆（CARR）作为应用平台开展中子散射实验的重要系统。

Cold Neutron Source ( CNS ) is one of the important systems through which China Advanced Research Reactor ( CARR ) could be used as important application platform of Neutron Scattering Experiment .

土壤-结构动力相互作用（SSI）分析及楼层反应谱（FRS）计算是中国先进研究堆（CARR）工程抗震设计的重要环节。

Analysis of Soil-Structure Interaction ( SSI ) and calculation of Floor Response Spectrum ( FRS ) is substantial for anti-seismic design for China Advanced Research Reactor ( CARR ) project .

SRAC程序在中国先进研究堆上的应用研究

Application of SRAC System on China Advanced Research Reactor

为了保证中国先进研究堆（CARR）的设计在安全上达到当代核安全水平，在技术上达到世界先进水平，建立了一套适用于CARR工程设计的标准体系。

A set of criterion system was set up for the design of CARR , to insure that the design satisfies the present requirements on the nuclear safety level and adopts the world advanced technology .

介绍了中国先进研究堆（CARR）氦气系统的方案调研、工艺流程设计、设备管道阀门布置设计和系统设计难点及特点。

The scheme , flow design and arrangements of equipment , pipe , valve and the characteristic and technical difficulties of helium system of China advanced research reactor ( CARR ) are introduced in the paper .

对中国在建的核功率为60MW的中国先进研究堆中冷中子源系统的设计作了总体描述。

A general description of the currently constructed CNS system in CARR with nuclear power of 60 MW is made .

开展中子散射工作是建造中国先进研究堆（简称CARR）的王要目的之一，建造有关的中子散射谱仪及相关设备是CARR工程的一部分。

One of the main purposes of building China Advanced Research Reactor ( CARR ) is to do neutron scattering experiments , it is one part of CARR project to set up neutron scattering spectrometers and relative equipments .

为研究堆浸工艺的机理，用逆Broyden秩1迭代公式寻求浸润面非线性方程的数值解，得到了满意的数值结果。

To study the mechanism of heap leaching process , Single rank inverse Broyden iterative method is applied to find the solution for nonlinear infiltrates surface equation and satisfying numerical results are obtained .

利用研究堆冷中子源装置提供的冷中子进行中子散射实验，已在众多基础科学和应用科学领域得到了广泛的应用，中子散射尤其是冷中子散射是CARR最重要的应用。

Cold Neutrons , provided by Cold Neutron Source ( CNS ) on research reactor , have been used for conducting neutron scattering experiments , which has been getting wider and wider applications in many fundamental and applied science fields .

以中国先进研究堆（CARR）最严重的失控提棒ATWS为例，对CARR事故缓解系统设计改进造成的影响进行分析。

The safety analysis of ATWS accident mitigating system improving design , based on the most serious case & ATWS induced by uncontrolled control rod withdrawal is performed for China Advanced Research Reactor ( CARR ) .