核电站安全参数显示系统的研究与设计

简要介绍了核电厂安全参数显示系统（ＳＰＤＳ）的设计特点和系统功能特点,包括设计准则、系统结构、多级显示、人因原则、自动诊断以及对ＳＰＤＳ的检验手段等。     

ADSP2101FEL－ICE开发系统

本文介绍了一种数字信号处理器（ＡＤＳＰ－２１０１）的开发系统──ＡＤＳＰ２１０ＩＦＥＬ－ＩＣＥ。描述了它的基本功能和设计思想。     

工控机CPU模板的设计

本文简要介绍所设计的ＳＴＤＭＣＳ－５１ＣＰＵ模板的基本结构和特点，重点阐述了该模板中应用和ＰＳＤ３１１大规模芯片的特点及设计方法，对ＰＳＤ３１１配置的设置及Ａ．Ｂ．Ｃ口的应用做了详细的论述。     

稳压器排放系统应力分析评定和管道支撑布置

介绍了泰山核电二期工程稳压器排放系统应力分析评定和管道布置及支撑调整过程，即采用ＰＤＬ－ＳＹＳＰＩＰＥ ＩＮＴＥＲＦＡＣＥ接口软件在三维ＣＡＤ工程设计系统ＰＤＬ中截取系统的各种特性参数，并将这些特性参数作为专用管道系统应力分析程序ＳＹＳＰＩＰＥ计算输入，在此基础上，利用ＳＹＳＰＩＰＥ程序的快速应力分析功能调整管道布置、支撑布置和支撑类型，并对管道承受的自重、内压、热膨胀、地震、破管和超压排放等载荷     

多路望远镜系统中的电子学和粒子分辨技术

本文介绍了多路望镜系统中的电子学系统和在测量核反应双微分截面实验中所使用的粒子分辨技术，该系统除了用能损△Ｅ谱和脉冲形状分辨ＰＳＤ谱来鉴别粒子外，还使用二维粒子分辨技术即用Ｅ－△，Ｅ－ＰＳＤ和△Ｅ－ＰＳＤ等谱来联合临别别粒子，取得了极好的分辨效果。     

TC13磁带机适配器在数据获取系统中的应用

ＭＯＤＡＳⅡ是基于ＰＤＰ－１１，全汇编的ＳＴＡＮＤ－ＡＬＯＮＧ数据获取系统。它采用ＤＭＡ方式，硬件排零。但磁带机系统ＴＭ１１速度较慢。为此，我们换用了ＴＣ１３磁带机系统，编写了相应的磁带机驱动程序，使系统的工作效率得到很大提高。     

数据获取系统中的TC13磁带机

ＭＯＤＡＳⅡ是基于ＰＤＰ－１１，全汇编的ＳＴＡＮＤ－ＡＬＯＮＧ数据获取系统。它采用ＤＭＡ方式，硬件排零。但磁带机系统ＴＭ１１速度较慢，为此，我们换用了ＴＣ１３磁带机系统，编写了相应的磁带机驱动程序，使系统的工作效率得到很大提高。     

基于DSP的智能模数变换插件设计

介绍了一个基于ＤＳＰ，用于采集北京谱仪实验数据的智能模数变换插件的设计方法。此插件是为替代ＳＬＡＣ于８０年代生产的类产品而设计的。插件上的ＤＳＰ实现了实时数据预处理功能。同时使用了ＦＰＧＡ构造ＶＭＥ总线接口，提高了集成度。     

测进电缆遥传系统

应用计算机，单片机和ＢＤＰＳＫ数字调制技术设计，研制了测井电缆遥传系统、该系统遥传速率为１００ｋｂ／ｓ，遥传距离为７ｋｍ，误码率小于１０＾－６。     

测井电缆遥传系统

应用计算机、单片机和ＢＤＰＳＫ数字调制技术设计、研制了测井电缆遥传系统，该系统遥传速率为１００ｋｂ／ｓ，遥传距离７ｋｍ，误码率小于１０－６。     

Emergency Response Capabilities-Past and Present

This paper focusses on emergency response capabilities at nuclear plants with the TMI-2 accident in perspective. The major thesis is that accident prevention by plant operators is the keystone, and the development of the Safety Parameter Display Systems (SPDS) is an essential operator's aid for thinking-through, and formulating strategies for preventing serious accidents from occuring. Human limits for processing information under stress is matched to the SPDS capability for displaying key plant safety variables in a concise, readily understandable manner. The industry response and general experience with the SPDS is reviewed. It is suggested that the SPDS, together with the development of intelligent routines, will play a major role in future improvements in emergency response capability.     

Signal validation techniques and power plant applications

Computerized signal validation is a software technique for integrating information from redundant and from functionally diverse sensors to provide highly reliable information to operating crews and to auto matic controllers. High reliability results from greater and more comprehensive use of existing sensor redundancy, and from inherent fault detection and isolation (FDI) of faulty sensors.

Operating crews at power plants have always performed some measure of manual signal validation. With the current thrust to introduce digital computers to support plant monitoring and operator aid functions# signal validation has become generally recognized as a key element in the interface between plant sensors and algorithms using sensor data. For any computerized system to be robust and to yield a false alarm rate that is credibly low, high information reliability must be assured at the front end.

Progress of research in computerized signal validation techniques has benefited the U.S. utilities by improving the reliability of safety parameter display systems (SPDS) implemented in the nuclear power plants. Conventional signal validation techniques have been combined with more robust parity space and analytic redundancy methods to provide reliable and real-time SPDS monitoring information to PWR and BWR operators. The technical details of the methods, application to PWR and BWR SPDS, and the extension of the techniques to plant control functions are reviewed in this paper.     

An analysis of the water-level monitoring system for a boiling-water reactor

The water-level instrumentation system is very important to the overall safety of a BWR. This system is being monitored by the Safety Parameter Display System (SPDS) that is being installed in Georgia Power Company's Plant Hatch. One of the most significant functions of the SPDS is the comparison of redundant instrument readings and formation of the best estimate of each parameter from those readings which are consistent. When comparing water-level instrument readings, it is necessary to correct the individual readings for differences between current and calibration conditions as well as for differences between calibration conditions for the multiple instruments. This paper documents the examination of the water-level instrumentation system at Plant Hatch and presents the development of the equations that were used to determine the differences between indicated and actual water levels.     

Signal validation with control-room information-processing computers

One of the ‘lessons learned’ from the Three Mile Island accident focuses upon the need for a validated source of plant-status information in the control room. The utilization of computer-generated graphics to display the readings of the major plant instrumentation has introduced the capability of validating signals prior to their presentation to the reactor operations staff. The current operations philosophies allow the operator a quick look at the gauges to form an impression of the fraction of full scale as the basis for knowledge of the current plant conditions. After the introduction of a computer-based information-display system such as the Safety Parameter Display System (SPDS), operational decisions can be based upon precise knowledge of the parameters that define the operation of the reactor and auxiliary systems. The principal impact of this system on the operator will be to remove the continuing concern for the validity of the instruments which provide the information that governs the operator's decisions.     

原发性高血压病患者99Tcm-MIBI心肌显像及其左室心肌质量测定

对33例临床确诊的原发性高血压病患者和18例正常对照者进行常规^99Tc^m—MIBI心肌显像后重建HSA、HVA和LVA，并对图像进行分析和打印，利用体视学原理测定左室心肌质量，以探讨原发性高血压病患者左室心肌质量的改变情况。结果表明，心肌显像结合体视学方法测定左室心肌质量可行且有效，用该方法可测定原发性高血压病患者左室心肌质量，还可同时观察心肌的血供和结构改变情况。     

Elemental analysis of agricultural soil samples by particle induced X-ray emission (PIXE) technique

In agriculture, elements essential to vital processes are also called nutrients. A suitable and reliable particle induced X-ray emission (PIXE) methodology for content determination of essential nutrients in soil samples was developed and its effectiveness proved. The PIXE method is applied to intermediate thickness samples, whose mass per area unit are smaller than 1 μg/cm². Precision and accuracy of the method was estimated after repeated measurements of a single reference material: CRM PACS-2 (estuarine sediment) with a matrix quite similar to the soil samples measured. This paper reports the results of elemental measurements in soil samples. A discussion of agricultural soil sample preparation for PIXE analysis is also presented.     

浅谈我国核电厂重要厂用水系统换热器隔离阀门与放射性监测仪表配置优化

对于运行核电厂来说,重要厂用水系统与质量和安全密切相关.核电厂重要厂用水系统用于导出设备冷却水系统所传输的热量,将其输送到海水中,因此是核岛的最终热阱.本文描述了当前我国大部分核电厂重要厂用水系统换热器隔离阀门与放射性监测仪表的配置现状,分析了包括美国、法国以及国际原子能机构对于重要厂用水系统设计要求的相同点与不同点,...     

解毒健脾中药选择性驱铅的实验研究

用醋酸铅建立铅中毒动物模型,以EDTA为对照,观察解毒健脾中药驱铅疗效及机理,结果表明:与正常组比较,EDTA组除血铅趋正常外,其余指标虽有明显改变但未恢复至正常(p<0.05),且驱铅同时尿中排出多种必需微量元素(p<0.05);中药组各项指标均恢复正常(p>0.05),尿中必需微量元素无改变(p>0.05)。对中药疗效优于EDTA的可能机理进行了讨论,认为中药可加速粪铅排出,降低肝铅积累;可使FEP恢复正常,显示驱铅的相对完全,中药驱铅而不干扰微量元素的体内平衡。     

核电运营企业的三个核心管理流程

以秦山第二核电厂的运营管理为例,从核电站生产工作组织过程,核安全重要岗位员工的培训、考核和授权流程,核电站财务预算管理流程三个方面论述了核电站运营管理中三个最核心流程的实施办法。掌握好、实施好这三个核心流程,就可以在最基本的管理层面上掌控核安全。