F70 辐射防护与监测综合 标准查询与下载

EJ 993-1996 铀矿冶辐射防护规定

Regulations on Radiation Protection of Uranium Mining and Metallurgy

ASTM E1006-96 试验反应堆E706(Ⅱ)用的物理剂量测定结果的分析和解释

1.1 This practice covers the methodology summarized in Annex A 1 to be used in the analysis and interpretation of physics-dosimetry results from test reactors. 1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods that are in various stages of completion (see Matrix E 706). 1.3 Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, exposure units, and neutron spectrum adjustment methods. 1.4 This practice is directed towards the development and application of physics-dosimetry-metallurgical data obtained from test reactor irradiation experiments that are performed in support of the operation, licensing, and regulation of LWR nuclear power plants. It specifically addresses the physics-dosimetry aspects of the problem. Procedures related to the analysis, interpretation, and application of both test and power reactor physics-dosimetry-metallurgy results are addressed in Practices E 185, E 560, E 853, and E 1035, Matrix E 706(IE), Guide E 900, and Test Method E 646. 1.5 This standard may involve hazardous materials, operations, and equipment. 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 Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)

ASTM E944-96 反应堆监测时中子光谱调节法的应用

1.1 This guide covers the analysis and interpretation of the physics dosimetry for Light Water Reactor (LWR) surveillance programs. The main purpose is the application of adjustment methods to determine best estimates of neutron damage exposure parameters and their uncertainties. 1.2 This guide is also applicable to irradiation damage studies in research reactors. 1.3 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 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)

DIN 25482-4:1995 核辐射测量用探测极限和判定极限.第4部分:不考虑试样处理影响和仪器使用影响的计数α光谱测量

The scope of the document concerns that part of nuclear measurement technique, in which events are alpha-spectrometrically counted, especially when frequency distribution of measured heights of pulses (multi channel spectrum) is recorded. It takes into account only the statistical character of nuclear events and pulse counting and leaves out of consideration other influences (i.e. measuring geometry, the treatment of probes, the working up of probes for the measurement, of possibly variing selfabsorption, weighing aspects, enrichment or of the instability of the measuring device).#,,#

Limit of detection and limit of decision for nuclear radiation measurements - Part 4: Counting alphaspectrometric measurements, neglecting the influence of sample treatment and equipment used

EJ/T 979-1995 表面氡析出率测定积累法

Accumulation method for determination of surface radon exhalation rate

ASTM D3648-95 放射性物质测量的标准实施规范

1.1 These practices cover a review of the accepted counting practices currently used in radiochemical analyses. The practices are divided into four sections: Section General Information 5 to 10 Alpha Counting 11 to 21 Beta Counting 22 to 32 Gamma Counting 33 to 40 1.2 The general information sections contain information applicable to all types of radioactive measurements, while each of the other sections is specific for a particular type of radiation. 1.3 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 Practices for the Measurement of Radioactivity

EJ/T 850-1994 氚内照射监测大纲的最低要求

Minimum Requirements for Tritium Internal Exposure Monitoring Program

EJ/T 819-1994 压水堆核电厂辐射监测设计用文字代号和图形符号

Character codes and graphic symbols for radiation monitoring design of pressurized water reactor nuclear power plants

EJ/T 790-1993 运行辐射防护最优化纲要系统评审方法

Systematic review method for operational radiation protection optimization program

DIN 25482-1 Bb.1:1992 核幅射测量的验算极限和判定极限.不考虑样品处理影响的计数测量法.说明和示例

Limit of detection and limit of decision for nuclear radiation measurements; counting measurements neglecting the influence of sample treatment; comments and examples

DIN 6802-1:1991 中子剂量学.专业术语和定义

Neutron dosimetry; special terms and definitions

EJ/T 612-1991 核电厂场外应急计划的标准格式与内容

Standard format and content of off-site emergency plans for nuclear power plants

EJ/T 613-1991 铀矿冶设施安全分析报告的标准格式与内容

Standard format and content of safety analysis report for uranium mining and metallurgy facilities

EJ 588-1991 核燃料后处理厂退役辐射防护规定

Regulations on Radiation Protection for Decommissioning of Nuclear Fuel Reprocessing Plants

DIN 25400:1991 电离辐射的基本符号

The standard spezifies the basic symbol for ionizing radiation. It is normally used for signing places and objects at which or near which ionizing radiation can be expected.

Basic symbol for ionizing radiation

STAS 6048/1-1989 无线电干扰．防寄生振荡．无线电干扰源一般规则

Radio interference radio interference suppression by sources of radiointerference general requitements

DIN 25482-1:1989 核辐射测量的验算极限和鉴定极限.第1部分:不考虑样品处理影响的计数测量法

The scope of this standard concerns that part of nuclear measurement technique in which (for instance relating to probes) the number of events (especially pulses) is directly recorded. It takes into account only the statistical character of radioactive decay and pulse counting and leaves out of consideration other influences. It presumens the duration of measurement to be short compared with the halflife of radionuclides and neglects possible dead times of apparatur used. The purpose of the standard is to fix suitable characteristic values, permitting a neutral estimantion of possible detectable results of nuclear radiation and radioactivity measurements.#,,#

Limit of detection and limit of decision for nuclear radiation measurements; counting measurements neglecting the influence of sample treatment

EJ 380-1989 开放型放射牲物质实验室辐射防护设计规范

Code for radiation protection design of open radioactive material laboratory

EJ 348-1988 铀矿冶辐射防护设计规定

Radiation protection design regulations for uranium mining and metallurgy

EJ 346-1988 粒子加速器工程设施辐射防护设计规范

Code for radiation protection design of particle accelerator engineering facilities