This thesis describes the field erection process of the loop reactor and the assembly welding method of a pair of the axial-flow pump flanges.

The imported reactor fuel assembly MARIA program system is adapted to CYBER 825 computer in China Institute of Atomic Energy, and extensively used for a series of enriched uranium bare sphere critical assemblies.

在CYBER825计算机上移植了引进的反应堆燃料组件计算程序系统MARIA以后，又将该程序系统推广应用于加浓铀裸球临界装置。

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The dynamic response of the fuel assembly and fuel channel interaction during a seismic event is analyzed to study the structural characteristics of the reactor fuel assembly as part of the Daqing NHR 200 project.

结合大庆200MW低温核供热示范工程，针对有盒组件结构的具体特点，提出了地震工况下燃料组件与燃料元件盒相互作用的动态响应分析模型；

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This paper describes the model of calculating the flux distribution in two dimensional hexagonal geometry light water reactor fuel assembly by interface current method.

利用界面流法计算两维六角形轻水堆燃料组件内中子通量密度分布。

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Flow field measurements using LDA and numerical computation for rod bundle of reactor fuel assembly

反应堆燃料组件棒束流场的激光测试和计算

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VERA ( Versatile Experimental Reactor Assembly) Ventilation: Good general or local exhaust ventilation are required for usage.

通用实验性反应堆装置通风措施：需要使用适当的通风装置。

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A high temperature ( 270 ℃) pressurized water zero power reactor assembly is described. Its constructure and main design parameters are given.

本文概述了工作温度为270℃的轻水高温零功率反应堆装置，给出了它的结构与主要设计参数。

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A pressurized water zero power reactor assembly

高温零功率反应堆装置

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The reactor efficiency ratio of the reactor is more than twice that of traditional electrolysis reactor with homocentric circle arrangement electrodes.

数学推导证明，新型电解反应器与同心圆状电极电解反应器效率比大于2。

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Based on the analysis of various kinds of reactor's electrical accident. The principle and function of 500 kV collateral reactor protection arrangement are introduced.

在分析500kV并联电抗器的各种故障的基础上，介绍了相应的保护装置的原理及功能，并对保护装置的选型进行了分析。

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This paper calculates the thermal-hydraulic parameters of the reactor core in steady arrangement and the pulsed parameters of the pulsed core with the computer program PRTHA, PULSE and TEMPUL.

利用PRTHA、PULSE和TEMPUL程序分别计算了西安脉冲堆首循环稳态堆芯布置的热工水力参数和脉冲堆芯的脉冲参数。

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The result indicates that the reactor core arrangement satisfies the critical and control request, and can meet the purpose of spent fuel critical experiments.

计算结果表明，该装置的堆芯布置满足临界和控制要求，能够满足乏燃料临界实验的需求。

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The paper gives the design purpose, reactor core arrangement and control system of ADS experiment facility on reactor physics research. Some experiment work is introduced.

文章介绍了ADS反应堆物理研究中的实验装置设计目的、堆芯布置及控制系统，同时给出了ADS反应堆物理研究中的部分内容。

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Analysis of 500 kV Collateral Reactor Protection Arrangement and Type Selection Protection arrangement of electric motor in transformer substation

500kV并联电抗器保护配置及选型分析厂用电动机在变电所内的保护设置

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Reactor Core Arrangement Control System on ADS Reactor Physics Research

ADS反应堆物理研究中的堆芯布置及控制系统

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A method used in reactivity worth calculation for control rods of 10MW high temperature gas cooled reactor ( HTR 10) is described, in which the control rods are located at the reflector and directly near the core.

介绍了10MW高温气冷反应堆（HTR－10）位于反射层中的控制棒反应性当量的计算方法。

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The steady counting rates of neutron in reactor are measured by a conventional instrument ( the start-up devices) to calibrate reactivity worth of a control rod.

利用常规仪器（堆控制室中的启动装置）测得反应堆中稳定的中子计数率来刻度控制棒的反应性当量。

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Measurment of Differential and Integral Reactivity Worth for Soluble Boron Poison on Light Water Lattice of UO_2 Rods and Comparison of the Control Rod Reactivity Worth

铀水栅上硼溶液微分、积分价值测量及控制棒效率对比

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The reactivity worth of control rods at each phase of HTR 10, including initial, running in and balance phases, has been calculated by using this method.

文中给出了HTR－10各运行阶段（包括初装堆、过渡过程中期和后期、平衡换料等时期）的控制棒的反应性当量。

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Measurement of Control Rod Reactivity Worth and Core Total Excess Reactivity for Pulsed Reactor by Soluble Boron Poison Method

用硼中毒法进行脉冲堆控制棒效率和总后备反应性测量

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Reactivity worth calculation for the control rods and secondary shutdown system of HTR-10

HTR－10控制棒及第二停堆系统反应性当量计算

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