F82 堆用核仪器 标准查询与下载

ASTM E910-01 反应堆容器监测用氦聚集流监视器的应用及分析的标准试验方法.E 706(IIIC)

1.1 This test method describes the concept and use of helium accumulation for neutron fluence dosimetry for reactor vessel surveillance. Although this test method is directed toward applications in vessel surveillance, the concepts and techniques are equally applicable to the general field of neutron dosimetry. The various applications of this test method for reactor vessel surveillance are as follows:1.1.1 Helium accumulation fluence monitor (HAFM) capsules,1.1.2 Unencapsulated, or cadmium or gadolinium covered, radiometric monitors (RM) and HAFM wires for helium analysis,1.1.3 Charpy test block samples for helium accumulation, and1.1.4 Reactor vessel (RV) wall samples for helium accumulation.1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

EJ/T 759.1-2000 核电厂控制室 控制器和屏幕显示的应用 第1部分：控制器

本标准规定了核电厂控制室专用系统.通用常规系统和软操系统的人机接口要求。 本标准适用于按 GB/T 13630-92 的要求设计的核电厂主控制室。 若要將本标准用於輔助控制點 或就地控制室的设计，或用于现有控制室的改建设计时，则应特别注意本标准所作的假设(如自动化程 度等)可能并不适用。

Applications of controllers and screen displays in nuclear power plant control rooms Part 1: Controllers

EJ/T 1060-1998 数字计算机在核电厂仪表和控制中的应用

Application of digital computers to instrumentation and control in nuclear power plant

EJ/T 1065-1998 核电厂仪表和控制设备的接地和屏蔽设计准则

The grounding and shielding design criterion for instrumentation and control equipment in nuclear power plant

EJ/T 1058-1998 核电厂安全系统计算机软件

本标准规定了为获得高可靠软件，对软件产生过程中的每个阶段（包括设计、研制、检验、鉴定与运行）以及每个阶段中的文件档案的基本要求及应遵循的原则。 本标准适用于核电厂安全系统中用于执行安全功能的计算机所要求的高可靠软件。

Software for computers in the safety systems of nuclear power plants

ASTM E854-98 反应堆监测用固态径迹记录仪(SSTR)监视器的应用和分析的试验方法,E 706(IIIB)

1.1 This test method describes the use of solid-state track recorders (SSTR) for neutron dosimetry in light-water reactor (LWR) applications. These applications extend from low neutron fluence to high neutron fluence, including high power pressure vessel surveillance and test reactor irradiations as well as low power benchmark field measurement. This test method replaces Method E418. This test method is more detailed and special attention is given to the use of state-of-the-art manual and automated track counting methods to attain high absolute accuracies. In-situ dosimetry in actual high fluence-high temperature LWR environs is emphasized. 1.2 This test method includes SSTR analysis by both manual and automated methods. To attain a desired accuracy, the track scanning method selected places limits on the allowable track density. Typically good results are obtained in the range of 5 to 500 000 tracks/cm and accurate results at higher track densities have been demonstrated for some cases. Track density and other factors place limits on the applicability of the SSTR method at high fluences. Special care must be exerted when measuring neutron fluences (E>1MeV) above 10 16 n/cm . 1.3 High fluence limitations exist. Successful results have been reported for total fluences up to approximately 10 16 n/cm . Beyond 10 16 n/cm some workers report problems (1), but others report no problems with total fluences up to approximately 5 X 10 18 n/cm (2). 1.4 SSTR observations provide time-integrated reaction rates. Therefore, SSTR are truly passive-fluence detectors. They provide permanent records of dosimetry experiments without the need for time-dependent corrections, such as decay factors that arise with radiometric monitors. 1.5 Since SSTR provide a spatial record of the time-integrated reaction rate at a microscopic level, they can be used for "fine-structure" measurements. For example, spatial distributions of isotopic fission rates can be obtained at very high resolution with SSTR. 1.6 This standard does not purport to address the safety problems associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)

EJ/T 1046-1997 核安全级CEC系列电容式变送器

CEC series capacitance transmitter for nuclear-safety

ASTM E844-97 E-706(ⅡC)反应堆监视用传感器装置设计和辐照的标准指南

1.1 This guide covers the selection, design, irradiation, post-irradiation handling, and quality control of neutron dosimeters (sensors), thermal neutron shields, and capsules for reactor surveillance neutron dosimetry. 1.2 The values stated in inch-pound units are to be regarded as the standard. The values given in parentheses are for information only. 1.3 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)

DIN 25702:1995 核素单位放射性测量用检波器屏蔽.带锗检波器的标准系统

The document deals with gamma radiation measuring places for the measurement of radioactive materials with low specific activity with energies between 40 keV to 2 MeV and with detector systems being hided in a shielding chamber. The document deals with standard systems for routine applications with measuring times of 1 hour and a limit of detection of about 1 Bq/kg.

Shieldings for detectors for nuclide-specific activity measurements - Standard-systems with germanium detectors

ASTM E910-95 反应堆容器监测用氦聚集流监视器的应用及分析的标准试验方法.E 706(IIIC)

1.1 This test method describes the concept and use of helium accumulation for neutron fluence dosimetry for reactor vessel surveillance. Although this test method is directed toward applications in vessel surveillance, the concepts and techniques are equally applicable to the general field of neutron dosimetry. The various applications of this test method for reactor vessel surveillance are as follows:1.1.1 Helium accumulation fluence monitor (HAFM) capsules,1.1.2 Unencapsulated, or cadmium or gadolinium covered, radiometric monitors (RM) and HAFM wires for helium analysis,1.1.3 Charpy test block samples for helium accumulation, and1.1.4 Reactor vessel (RV) wall samples for helium accumulation.1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

IEC 61304:1994 核仪器 液体 闪烁计数系统 性能验证

The purpose is to provide the user with a means of verifying the performance of typical LSC systems. Measures of performance considered are counting system efficiency and reproducibility of sample and background count rates. Deals with sources and materi

Nuclear instrumentation - Liquid-scintillation counting systems - Performance verification

EJ/T 778-1993 铀氢锆脉冲堆辐射监测系统设计准则

Design criteria for radiation monitoring system of uranium hydrogen zirconium pulsed reactor

EJ/T 800.1-1993 反应堆用抗震、耐振机箱和机柜通用技术条件 地面固定型

General specifications for anti-seismic and anti-vibration chassis and cabinets for reactors Ground-fixed type

EJ/T 800.2-1993 反应堆用抗震、耐振机箱和机柜通用技术条件 舰载型

General technical requirements for anti-seismic and anti-vibration chassis and cabinets for reactors Shipborne type

EJ/T 760-1993 核电厂安全重要仪表和控制系统的供电要求

Power supply requirements for instrumentation and control systems important to safety in nuclear power plants

EJ/T 762-1993 脉冲堆核测量系统设计准则

Design Criteria for Pulse Reactor Nuclear Measurement System

EJ/T 747-1992 压水堆核电厂一回路系统、设备化学去污导则

Guidelines for chemical decontamination of primary circuit systems and equipment in pressurized water reactor nuclear power plants

EJ/T 673-1992 核电厂保护系统敏感元件和传感器型式检验准则

本标准规定了核电厂保护系统敏感元件和传感器的型式检验准则和文件编制的要求。 本标准适用于核电厂保护系统敏感元件和传感器的型式检验（包括对新研制或改进的敏感元件和传感器的检验，但不包括已根据EJ/T 609进行过型式检验的传感器电气插件）。

Criteria for Type Inspection of Sensitive Components and Sensors of Nuclear Power Plant Protection System

EJ/T 331-1992 失水事故后流体系统的安全壳隔离装置

Containment Isolation Devices for Fluid Systems Following a Loss of Water Accident

EJ/T 667-1992 与反应堆冷却剂压力边界相连的低压系统的超压保护

Overpressure protection for low pressure systems connected to reactor coolant pressure boundaries