F74 辐射防护监测与评价 标准查询与下载

ASTM E481-10 钴和银放射性活化法测定中子注量率的标准试验方法

The pertinent data for these two reactions are given in Table 1. This test method uses one monitor (cobalt) with a nearly 1/v absorption cross-section curve and a second monitor (silver) with a large resonance peak so that its resonance integral is large compared to the thermal cross section. The equations are based on the Westcott formalism (2, 3) and determine a Westcott 2200 m/s neutron fluence rate nv0 and the Westcott epithermal index parameter r1.1 This test method covers a suitable means of obtaining the thermal neutron fluence rate, or fluence, in well moderated nuclear reactor environments where the use of cadmium, as a thermal neutron shield as described in Method E262, is undesirable because of potential spectrum perturbations or of temperatures above the melting point of cadmium. 1.2 This test method describes a means of measuring a Westcott neutron fluence rate (Note 1) by activation of cobalt- and silver-foil monitors (See Terminology E170). The reaction 59Co(n,γ)60Co results in a well-defined gamma emitter having a half-life of 1925.28 days (1). The reaction 109Ag(n,˙γ) 110mAg results in a nuclide with a complex decay scheme which is well known and having a half-life of 249.76 days (1). Both cobalt and silver are available either in very pure form or alloyed with other metals such as aluminum. A reference source of cobalt in aluminum alloy to serve as a neutron fluence rate monitor wire standard is available from the National Institute of Standards and Technology (NIST) as Standard Reference Material 953. The competing activities from neutron activation of other isotopes are eliminated, for the most part, by waiting for the short-lived products to die out before counting. With suitable techniques, thermal neutron fluence rate in the range from 109 cm−2 · s−1 to 3 × 1015 cm−2 · s−1 can be measured. For this method to be applicable, the reactor must be well moderated and be well represented by a Maxwellian low-energy distribution and an (1/E) epithermal distribution. These conditions are usually met in positions surrounded by hydrogenous moderator without nearby strongly absorbing materials. Otherwise the true spectrum must be calculated to obtain effective activation cross sections over all energies.

Standard Test Method for Measuring Neutron Fluence Rate by Radioactivation of Cobalt and Silver

ANSI N13.6-2010 职业辐射暴露记录系统实施规程

This standard provides guidance to the facility operator for systematic creation, scheduling, retention, and disposition of records related to occupational radiation exposure.

Practice for Occupational Radiation Exposure Records Systems

ASTM E2420-10 放射污染设备后钝化监督和维护标准指南

The purpose of this guide is to provide the user information and guidance for preparation of a plan for the surveillance and maintenance of nuclear facilities that have been deactivated and are awaiting D&D. This document provides guidance for performing S&M in a way that will ensure worker and public safety, while also addressing stakeholder requirements. Use of this guide helps standardize the basic requirements for S&M of nuclear facilities. Use of this guide helps ensure that the S&M plan addresses the significant activities and actions necessary to maintain these facilities in a safe and stable condition until they can be decommissioned.1.1 This guide outlines a method for developing a Surveillance and Maintenance (S&M) plan for inactive nuclear facilities. It describes the steps and activities necessary to prevent loss or release of radioactive or hazardous materials, and to minimize physical risks between the deactivation phase and the start of facility decontamination and decommissioning (D&D). 1.2 The primary concerns for S&M are related to (1) animal intrusion, (2) structural integrity degradation, (3) water in-leakage, (4) contamination migration, (5) unauthorized personnel entry, and (6) theft/intrusion. This document is intended to serve as a guide only, and is not intended to modify existing regulations.

Standard Guide for Post-Deactivation Surveillance and Maintenance of Radiologically Contaminated Facilities

ASTM E170-10 辐射测量和剂量测定相关标准术语

Standard Terminology Relating to Radiation Measurements and Dosimetry

ASTM E1249-10 用钴60源以最大程度上减少硅电子装置辐射强度试验的剂量测定误差的标准操作规程

Division of the Co-60 Hardness Testing into Five Parts: The equilibrium absorbed dose shall be measured with a dosimeter, such as a TLD, located adjacent to the device under test. Alternatively, a dosimeter may be irradiated in the position of the device before or after irradiation of the device. This absorbed dose measured by the dosimeter shall be converted to the equilibrium absorbed dose in the material of interest within the critical region within the device under test, for example the SiO 2 gate oxide of an MOS device. A correction for absorbed-dose enhancement effects shall be considered. This correction is dependent upon the photon energy that strikes the device under test. A correlation should be made between the absorbed dose in the critical region (for example, the gate oxide mentioned in 4.1.2) and some electrically important effect (such as charge trapped at the Si/SiO2 interface as manifested by a shift in threshold voltage). An extrapolation should then be made from the results of the test to the results that would be expected for the device under test under actual operating conditions.1.1 This practice covers recommended procedures for the use of dosimeters, such as thermoluminescent dosimeters (TLD's), to determine the absorbed dose in a region of interest within an electronic device irradiated using a Co-60 source. Co-60 sources are commonly used for the absorbed dose testing of silicon electronic devices. Note 18212;This absorbed-dose testing is sometimes called “total dose testing” to distinguish it from “dose rate testing.” Note 28212;The effects of ionizing radiation on some types of electronic devices may depend on both the absorbed dose and the absorbed dose rate; that is, the effects may be different if the device is irradiated to the same absorbed-dose level at different absorbed-dose rates. Absorbed-dose rate effects are not covered in this practice but should be considered in radiation hardness testing. 1.2 The principal potential error for the measurement of absorbed dose in electronic devices arises from non-equilibrium energy deposition effects in the vicinity of material interfaces. 1.3 Information is given about absorbed-dose enhancement effects in the vicinity of material interfaces. The sensitivity of such effects to low energy components in the Co-60 photon energy spectrum is emphasized. 1.4 A brief description is given of typical Co-60 sources with special emphasis on the presence of low energy components in the photon energy spectrum output from such sources. 1.5 Procedures are given for minimizing the low energy components of the photon energy spectrum from Co-60 sources, using filtration. The use of a filter box to achieve such filtration is recommended. 1.6 Information is given on absorbed-dose enhancement effects that are dependent on the device orientation with respect to the Co-60 source. 1.7 The use of spectrum filtration and appropriate device orientation provides a radiation environment whereby the absorbed dose in the sensitive region of an electronic device can be calculated within defined error limits without detailed knowledge of either the device structure or of the photon energy spectrum of the source, and hence, without knowing the details of the absorbed-dose enhancement effects. 1.8 The recommendations of this practice are primarily applicable to piece-part testing of electronic devices. ......

Standard Practice for Minimizing Dosimetry Errors in Radiation Hardness Testing of Silicon Electronic Devices Using Co-60 Sources

ANSI/ANS 2.17-2010 核电站地表下放射性核素迁移的评定

This national standard establishes the requirements for evaluating the occurrence and movement of radionuclides in the subsurface resulting from abnormal radionuclide releases at commercial nuclear power plants.

Evaluation of Subsurface Radionuclide Transport at Commercial Nuclear Power Plants

ANSI/ASTM E2116:2010 自带干藏γ射线辐射仪剂量测定的实施规范

Practice for Dosimetry for a Self-Contained Dry-Storage Gamma-Ray Irradiator

ANSI/ASTM E2232:2010 放射处理过程中吸收剂量计算数学方法的选择和使用指南

Guide for Selection and Use of Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications

JIS Z 4601:2009 放射性尘埃

This Japanese Industrial Standard was established in November 1958 and has gone through five refisions to this day.

Radioactive dust samplers

NF M60-525*NF ISO 21243:2009 辐射防护.辐射或核紧急事件中大量人员伤亡评定用实验室实施细胞遗传治疗类选法的性能标准.申请双着丝粒鉴定和一般原则

Radiation protection - Performance criteria for laboratories performing cytogenetic triage for assessment of mass casualties in radiological or nuclear emergencies - General principles and application to dicentric assay.

DIN 25475-2:2009 核设施 操作监控 第2部分:受压水反应堆中初级冷却电路振动特性改变的早期探测用振动监控

This standard applies to procedures for early detection of changes in the vibration of the components of the primary circuit, the reactor pressure vessel internals, and main coolant pump shafts of pressurized water reactors.

Nuclear facilities - Operational monitoring - Part 2: Vibration monitoring for early detection of changes in the vibrational behavior of the primary coolant circuit in pressurized water reactors

IEC 61559-1:2009 核设施辐射.连续监测辐射和/或放射性水平的集中式系统.第1部分：一般要求

Radiation protection instrumentation in nuclear facilities - Centralized systems for continous monitoring of radiation and/or levels of radioactivity - Part 1: General requirements

NF M60-761-2:2009 核能.环境中放射性测量.水.第2部分:水中氡222及其短期子体产物:用伽马光谱测定法测量

Nuclear energy - Measurement of radioactivity in the environment - Water - Part 2 : radon 222 and its short-life daughter products in water : measurements by gamma spectrometry.

DIN 54115-5:2009 无损检验.密封放射性源技术应用的辐射防护规则.第5部分:γ射线照相的辐射预防措施的建立

Non-destructive testing - Radiation protection rules for the technical application of sealed radioactive sources - Part 5: Building precautionary measures of radiation protection for the gammaradiography

ANSI N43.17-2009 使用X-射线或γ辐射的个人安全防护系统的辐射安全性

Applies to the manufacture & operation of security screening systems that use x rays, gamma radiatioin or both in which individuals are intentionally exposed to this ionizing radiation. Does not address neutron-based systems. The standard provides requirements specific to the ionizing radiation safety aspects of both the design and operation of these systems. It does not include electrical safety guidelines or any other safety, performance or use considerations outside of the realm of radiation safety.

Radiation Safety for Personnel Security Screening Systems Using X-ray or Gamma Radiation

ANSI N13.53-2009 技术提升自然存在的放射性物质(TENORM)的控制和释放

The purpose of this standard is to provide general guidance and normative criteria for the control and release of technologically enhanced naturally occurring radioactive material. The activities considered by this standard include mining and benefication of ores; processing of ore material, gangue, and wastes; feedstock used in the manufacture of consumer and industrial products; and distribution of products containing TENORM.

Control and Release of Technologically Enhanced Naturally Occuring Radioactive Material (TENORM)

ASTM E2628-09e1 辐射加工剂量学的标准实施规程

Radiation processing of articles in both commercial and research applications may be carried out for a number of purposes. These include, for example, sterilization of health care products, reduction of the microbial populations in foods and modification of polymers. The radiations used may be accelerated electrons, gamma-radiation from radionuclide sources such as cobalt-60, or X-radiation. To demonstrate control of the radiation process, the absorbed dose must be measured using a dosimetry system, the calibration of which, is traceable to appropriate national or international standards. The radiation-induced change in the dosimeter is evaluated and related to absorbed dose through calibration. Dose measurements required for particular processes are described in other standards referenced in this practice.1.1 This practice describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E10.01 series of dosimetry standards. In addition, it provides guidance on the selection of dosimetry systems and directs the user to other standards that provide specific information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications. 1.2 This practice applies to dosimetry for radiation processing applications using electrons or photons (gamma- or X-radiation). 1.3 This practice addresses the minimum requirements of a measurement management system, but does not include general quality system requirements. 1.4 This practice does not address personnel dosimetry or medical dosimetry. 1.5 This practice does not apply to primary standard dosimetry systems. 1.6 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.

Practice for Dosimetry in Radiation Processing

ANSI N13.11-2009 人员放射量测定性能.测试标准

This standard applies to dosimetry systems used to determine personal dose equivalent for occupational conditions and absorbed dose for accident conditions. Tests are conducted under controlled conditions and include irradiation with photons, beta particles, neutrons and selected mixtures of these radiations.

Personnel Dosimetry Performance - Criteria for Testing

ASTM E2701-09 辐射处理用剂量计和剂量测量系统性能特征描述的标准指南

Ionizing radiation produces physical or chemical changes in many materials that can be measured and related to absorbed dose. Materials with radiation-induced changes that have been thoroughly studied can be used as dosimeters in radiation processing. Note 38212;The scientific basis for commonly used dosimetry systems and detailed descriptions of the radiation-induced interactions are given in ICRU Report 80. Before a material can be considered for use as a dosimeter, certain characteristics related to manufacture and measurement of its response to ionizing radiation need to be considered, including: the ability to manufacture batches of the material with evidence demonstrating a reproducible radiation-induced change, nbsp;nbsp;nbsp;the availability of instrumentation for measuring this change, and the ability to take into account effects of influence quantities on the dosimeter response and on the measured absorbed-dose values. Dosimeter/dosimetry system characterization is conducted to determine the performance characteristics for a dosimeter/dosimetry system related to its capability for measuring absorbed dose. The information obtained from dosimeter/dosimetry system characterization includes the reproducibility of the measured absorbed-dose value, the useful absorbed-dose range, effects of influence quantities, and the conditions under which the dosimeters can be calibrated and used effectively. Note 48212;When dosimetry systems are calibrated under the conditions of use, effects of influence quantities may be minimized or eliminated, because the effects can be accounted for or incorporated into the calibration method (see ISO/ASTM Guide 51261). nbsp;nbsp;nbsp;The influence quantities of importance might differ for different radiation processing applications and facilities. For references to standards describing different applications and facilities, see Practice E 2628. Classification of a dosimeter as a type I dosimeter or a type II dosimeter (see Practice E 2628) is based on performance characteristics related to the effects of influence quantities obtained from dosimeter/dosimetry system characterization. nbsp;nbsp;nbsp;The dosimeter manufacturer or supplier is responsible for providing a product that meets the performance characteristics defined in product specifications, certificates of conformance, or similar types of documents. Dosimeter specifications should be developed based on dosimeter/dosimetry system characterization. The user has the responsibility for ensuring that the dosimetry requirements for the specific applications are met and that dosimeter/dosimetry system characterization information has been considered in: determining the suitability of the dosimeter or dosimetry system for the specific application (see Practice E 2628), nbsp;nbsp;nbsp;selecting the calibration method (see ISO/ASTM Guide 51261), establishing dosimetry system operational procedures (see respective dosimetry system practice listed in Practice E 2628), and nbsp;nbsp;nbsp;estimating the uncertainty components in the measured dose values (see ISO/ASTM Guide 51707). Dosimeter/dosimetry system characterization information provided by manufacturers or suppliers, or available in the literature, should be reviewed by the user to determine the tests that should be performed prior to the use of the dosimeter or dosimetry system. Information on performance characteristics should be verified before using.1.1 This guide provides guidance on determining the performance characteristics of dosimeters and dosimetry systems used in radiation processing. 1.2 This guide describes the infl......

Standard Guide for Performance Characterization of Dosimeters and Dosimetry Systems for Use in Radiation Processing

ASTM E2731-09 放射性扩散事件后用以减轻放射性污染蔓延的材料的标准规范

1.1 This specification is intended to provide a basis for identification of materials used to immobilize radioactive contamination, minimize exposure, and facilitate subsequent decontamination. 1.2 This standard provides a set of specifications describing a stabilizer (coating or coating system) to be used to prevent the spread of radioactive contamination. Some of these specifications may prove difficult to meet. A product that meets some, but not all, of the performance specifications herein may have value, and this specification may be used as a guide by which to evaluate such products. 1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1.4 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 Specification for Materials to Mitigate the Spread of Radioactive Contamination after a Radiological Dispersion Event