F92 工农业用加速器 标准查询与下载

GB/T 41985-2022 230MeV~250MeV超导质子回旋加速器

本文件规定了230 MeV~250 MeV超导质子回旋加速器(以下简称“加速器”)的基本组成和工作条件、技术要求、试验方法、检验规则以及标志、包装、运输、贮存和随行文件。 本文件适用于质子能量为230 MeV~250 MeV,束流强度为1nA~1000nA的超导质子回旋加速器。 本文件不适用于同步回旋加速器。

230MeV~250MeV superconducting proton cyclotron

GB/T 34127-2017 10 MeV～20 MeV范围内固定能量强流质子回旋加速器

Fixed energy high intensity proton cyclotron within the range of 10 MeV～20 MeV

GB/T 34128-2017 15 MeV～30 MeV可变能量强流质子回旋加速器

15 MeV～30 MeV variable energy high intensity proton cyclotron

T/CIRA 10-2020 辐射交联氯化聚乙烯绝缘电缆

本文件结构包括目次、前言、和章节内容。 章节具体内容包括范围、规范性引用文件、术语及定义、电缆型号及产品名称、单芯硬导体70℃辐射交联氯化聚乙烯无护套电缆、单芯软导体70℃辐射交联氯化聚乙烯无护套电缆、内部布线用导体温度为70℃的单芯硬导体辐射交联氯化聚乙烯无护套电缆、内部布线用导体温度为70℃的单芯软导体辐射交联氯化聚乙烯无护套电缆、内部布线用导体温度为90℃的单芯硬导体辐射交联氯化聚乙烯无护套电缆、内部布线用导体温度为90℃的单芯软导体辐射交联氯化聚乙烯无护套电缆、成品机械性能等。

Radiation crosslinked chlorinated polyethylene insulation cable

T/CNS 11-2019 纸包装光油电子束固化技术规范

本标准主要包括引言、前言、正文8个部分和1个附录，8个部分分别是1. 范围、2. 规范性引用文件、3. 术语与定义、4. 总体要求、5. 电子束固化装置技术要求、6. 固化工艺设计、7. 光油上光技术要求和8. 运行管理。附录A为低能电子加速器的深度剂量分布。 1. 范围：范围由原先的凹印光油上光扩大到纸包装光油上光，包括凹印、胶印、柔印等不同印刷方式的纸包装表面光油电子束固化，规定了纸包装光油电子束固化的术语和定义、总体要求以及电子束固化设备技术要求、固化工艺设计要求和光油上光技术要求等。 2. 规范性使用文件：列出本标准中引用到的其他标准的标准编号和名称，并按照标准序号由大到小进行排列。本标准中总用引用1项国际标准，11项国家标准，2项行业标准，1项团体标准和1项企业标准。 3. 术语与定义：该部分主要对纸包装光油电子束固化过程中常用的专业术语以及本标准中出现的需要特别解释的部分术语和定义。为了避免定义重复及标准的简练明了，未列出部分常用的简单类术语和一些非特异性术语，均可在其他标准或名词术语出版物中查询到。 4. 总体要求：主要从全过程的角度对需要注意的关键重点进行梳理和整合，包括车间环境、辐射安全、电子加速器装置、EB光油、印刷过程控制及成品质量要求，为后续每一部分内容的展开做铺垫。 5. 电子束固化装置技术要求：本部分是标准的重点内容之一，从电子加速器装置、束下装置、射线屏蔽和控制系统4各方面对电子束固化设备的组成及其各自的技术要求进行梳理和汇总，确保设备的可行性、稳定性、安全性和联动性，为纸包装光油的固化提供基础支持。 6. 固化工艺设计：固化工艺包括原材料、电子束能量、吸收剂量、辐照区域内氧浓度控制、阻氧控制等。纸包装光油电子束固化有别于UV固化的点主要包括原材料采用EB专用光油，无引发剂，同时辐照过程需要阻氧控制，避免氧气对固化效果的影响。因此本部分将工艺中的关键因素进行汇总并针对实际运行参数提出技术要求。 7. 光油上光技术要求：本部分主要根据光油上光过程需要注意的生产环节进行说明，包括上光车间环境要求、上光前准备、光油涂布量、操作要求和产品质量要求。从环境温、湿度、设备及材料的准备到上光的操作，每一环节都进行约束和说明，确保成品质量满足相关要求（外观、光泽度、VOCs和安全性要求、结合牢度、耐摩擦性、摩擦系数、爆线和色差）。 8. 运行管理：本部分主要对纸包装光油电子束固化的全过程管理，包括安装鉴定、运行鉴定、性能鉴定、成品放行、确认的审核和批准和记录。在运行过程中始终做好相关确认及记录存档，保证数据的可追溯性，有利于现场运行的跟踪与查证，保证运行的有效和稳定。 附录A：低能电子束的深度剂量分布，给出80 keV – 300 keV不同能量电子束标准穿透深度，不同能量，穿透的标准深度不同，可作为电子加速器能量选择的依据。

Specification of Electron Beam Curing of Varnish for Paper Packaging

IEC TR 62918:2014 核电厂. 具有安全重要性的仪表和控制. 具有安全重要性的系统集成无线装置的使用和选择技术报告

Nuclear power plants - Instrumentation and control important to safety - Technical report on use and selection of wireless devices to be integrated in systems important to safety

ISO/ASTM 52628:2013 辐射处理中剂量学的标准实施规程

This practice describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E61 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.

Standard practice for dosimetry in radiation processing

ASTM ISO/ASTM 52628-13 辐射加工过程中计量测定的标准实施规程

4.1 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. 4.2 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 E61 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.

Standard Practice for Dosimetry in Radiation Processing

ASTM ISO/ASTM 51261-13 辐射处理用常规剂量测定系统校准的标准实施规程

4.1 Ionizing radiation is used to produce various desired effects in products. Examples of applications include the sterilization of medical products, microbial reduction, modification of polymers and electronic devices, and curing of inks, coatings, and adhesives.4.2 Absorbed-dose measurements, with statistical controls and documentation, are necessary to ensure that products receive the desired absorbed dose. These controls include a program that addresses requirements for calibration of routine dosimetry system.4.3 A routine dosimetry system calibration procedure as described in this document provides the user with a dosimetry system whose dose measurements are traceable to national or international standards for the conditions of use (see Annex A4). The dosimetry system calibration is part of the user抯 measurement management system.1.1 This practice specifies the requirements for calibrating routine dosimetry systems for use in radiation processing, including establishing measurement traceability and estimating uncertainty in the measured dose using the calibrated dosimetry system.NOTE 1桼egulations or other directives exist in many countries that govern certain radiation processing applications such as sterilization of healthcare products and radiation processing of food requiring that absorbed-dose measurements be traceable to national or international standards (ISO 11137-1, Refs (1-3)2).1.2 The absorbed-dose range covered is up to 1 MGy.1.3 The radiation types covered are photons and electrons with energies from 80 keV to 25 MeV.1.4 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ASTM E2628 揚ractice for Dosimetry in Radiation Processing?for the calibration of routine dosimetry systems. It is intended to be read in conjunction with ASTM E2628 and the relevant ASTM or ISO/ASTM standard practice for the dosimetry system being calibrated referenced in Section 2.1.5 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 Calibration of Routine Dosimetry Systems for Radiation Processing

ASTM ISO/ASTM 52701-13 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

4.1 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 3—The scientific basis for commonly used dosimetry systems and detailed descriptions of the radiation-induced interactions are given in ICRU Report 80. 4.2 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: 4.2.1 the ability to manufacture batches of the material with evidence demonstrating a reproducible radiation-induced change, 4.2.2  the availability of instrumentation for measuring this change, and 4.2.3 the ability to take into account effects of influence quantities on the dosimeter response and on the measured absorbed-dose values. 4.3 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 4—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 Practice 51261). 4.4  The influence quantities of importance might differ for different radiation processing applications and facilities. For references to standards describing different applications and facilities, see ISO/ASTM Practice 52628. 4.5 Classification of a dosimeter as a type I dosimeter or a type II dosimeter (see ISO/ASTM Practice 52628) is based on performance characteristics related to the effects of influence quantities obtained from dosimeter/dosimetry system characterization. 4.6  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. 4.7 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: 4.7.1 determining the suitability of the dosimeter or dosimetry system for the specific application (see ISO/ASTM Practice 52628), 4.7.2  selecting the calibration method (see ISO/ASTM Guide 51261), 4.7.3 establishing dosimetry sy......

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

ASTM E2303-11e1 辐射加工设施中吸收剂量标记的标准指南

4. Significance and UseTop Bottom 4.1 This guide is one of a set of guides and practices that provide recommendations for properly implementing dosimetry in radiation processing. In order to understand and effectively use this and other dosimetry standards, consider first ???Practice for Dosimetry in Radiation Processing,??? ASTM Practice E2628, which describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E10.01 series of dosimetry standards. In addition, ASTM Practice E2628 provides guidance on the selection of dosimetry systems and directs the user to other standards that provide information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications. 4.2 Radiation processing is carried out under fixed path conditions where (a) a process load is automatically moved through the radiation field by mechanical means or (b) a process load is irradiated statically by manually placing product at predetermined positions before the process is started. In both cases the process is controlled in such a manner that the process load position(s) and orientation(s) are reproducible within specified limits.Note 2???Static irradiation encompasses irradiation of the process load using either manual rotation, no rotation or automated rotation. 4.3 Some radiation processing facilities that utilize a fixed conveyor path for routine processing may also characterize a region within the radiation field for static radiation processing, sometimes referred to as ???Off Carrier??? processing. 4.4 Many radiation processing applications require a minimum absorbed dose (to achieve a desired effect or to fulfill a legal requirement), and a maximum absorbed dose (to ensure that the product, material or substance still meets functional specifications or to fulfill a legal requirement). 4.5 Information from the dose mapping is used to: 4.5.1 Characterize the radiation process and assess the reproducibility of absorbed-dose values, which may be used as part of operational qualification and performance qualification. 4.5.2 Determine the spatial distribution of absorbed doses and the zone(s) of maximum and minimum absorbed doses throughout a process load, which may consist of an actual or simulated product. 4.5.3 Establish the relationship between the dose at a routine monitoring position and the dose within the minimum and maximum dose zones established for a process load. 4.5.4..........

Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities

ASTM F526-11 测定线性加速器脉冲发射效应试验用剂量的标准试验方法

An accurate measure of the dose is necessary to ensure the validity of the data taken, to enable comparison to be made of data taken at different facilities, and to verify that components or circuits are tested to the radiation specification applied to the system for which they are to be used. The primary value of a calorimetric method for measuring dose is that the results are absolute. They are based only on physical properties of materials, that is, the specific heat of the calorimeter-block material and the Seebeck EMF of the thermocouple used or the temperature coefficient of resistance (α) of the thermistor used, all of which can be established with non-radiation measurements. The method permits repeated measurements to be made without requiring entry into the radiation cell between measurements.1.1 This test method covers a calorimetric measurement of the total dose delivered in a single pulse of electrons from an electron linear accelerator or a flash X-ray machine (FXR, e-beam mode) used as an ionizing source in radiation-effects testing. The test method is designed for use with pulses of electrons in the energy range from 10 to 50 MeV and is only valid for cases in which both the calorimeter and the test specimen to be irradiated are“thin” compared to the range of these electrons in the materials of which they are constructed. 1.2 The procedure described can be used in those cases in which (1) the dose delivered in a single pulse is 5 Gy (matl) (500 rd (matl)) or greater, or (2) multiple pulses of a lower dose can be delivered in a short time compared to the thermal time constant of the calorimeter. Matl refers to the material of the calorimeter. The minimum dose per pulse that can be acceptably monitored depends on the variables of the particular test, including pulse rate, pulse uniformity, and the thermal time constant of the calorimeter. 1.3 A determination of the total dose is made directly for the material of which the calorimeter block is made. The total dose in other materials can be calculated from this measured value by formulas presented in this test method. The need for such calculations and the choice of materials for which calculations are to be made shall be subject to agreement by the parties to the test. 1.4 The values stated in SI units are to be regarded as the standard. The values in parenthesis are provided for information only. 1.5 This standard does not purport to address 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 Measuring Dose for Use in Linear Accelerator Pulsed Radiation Effects Tests

ASTM ISO/ASTM 51261-02 辐射处理用剂量测定体系的选择和校准的标准指

4.1 Ionizing radiation is used to produce various desired effects in products. Examples include the sterilization of medical products, processing of food, modification of polymers, irradiation of electronic devices, and curing of inks, coatings, and adhesives (1, 2) . The absorbed doses employed in these applications range from about 10 Gy to more than 100 kGy.4.2 Regulations for sterilization of medical products and radiation processing of food exist in many countries. These regulations may require that the response of the dosimetry system be calibrated and traceable to national standards (3, 4, 5). Adequate dosimetry, with proper statistical controls and documentation, is necessary to ensure that the products are properly processed. 4.3 Proper dosimetric measurements must be employed to ensure that the product receives the desired absorbed dose. The dosimeters must be calibrated. Calibration of a routine dosimetry system can be carried out directly in a national or accredited standards laboratory by standardized irradiation of routine dosimeters. Alternatively, it may be carried out through the use of a local (in-house) calibration facility (6) or in a production irradiator. All possible factors that may affect the response of dosimeters, including environmental conditions and variations of such conditions within a processing facility, should be known and taken into account. The associated analytical instrumentation must also be calibrated.1.1 This guide covers the basis for selecting and calibrating dosimetry systems used to measure absorbed dose in gamma-ray or X-ray fields and in electron beams used for radiation processing. It discusses the types of dosimetry systems that may be employed during calibration or on a routine basis as part of quality assurance in commercial radiation processing of products. This guide also discusses interpretation of absorbed dose and briefly outlines measurements of the uncertainties associated with the dosimetry. The details of the calibration of the analytical instrumentation are addressed in individual dosimetry system standard practices.1.2 The absorbed-dose range covered is up to 1 MGy (100 Mrad). Source energies covered are from 0.1 to 50 MeV photons and electrons.1.3 This guide should be used along with standard practices and guides for specific dosimetry systems and applications covered in other standards.1.4 Dosimetry for radiation processing with neutrons or heavy charged particles is not covered in this guide.1.5 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 Selection and Calibration of Dosimetry Systems for Radiation Processing

ANSI/IEEE 1205:2000 核电站用1E级设备老化影响的评定、监测和减轻

This document provides the guidelines for assessing, monitoring, and mitigating aging degradation effects on Class 1E equipment used in nuclear power generating stations. It also includes informative annexes on aging mechanisms, environmental monitoring, condition monitoring, aging program essential attributes, and example assessments for five types of equipment (including electric cable).

Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Sations

NF M62-105:1998 核能.工业加速器.安装

Nuclear energy. Industrial accelerators : installations.

ASTM F526-97 测定线性加速器脉冲发射效应试验用剂量的方法

1.1 This test method covers a calorimetric measurement of the dose delivered in a single pulse of electrons from an electron linear accelerator used as an ionizing source in radiation-effects testing. The test method is designed for use with pulses of electrons in the energy range from 10 to 50 MeV and is only valid for cases in which both the calorimeter and the test specimen to be irradiated are "thin" compared to the range of these electrons in the materials of which they are constructed. 1.2 The procedure described can be used in those cases in which (1) the dose delivered in a single pulse is 5 Gy (500 rad) or greater, or (2) multiple pulses of a lower dose can be delivered in a time short compared to the thermal time constant of the calorimeter. The minimum dose per pulse that can be acceptably monitored depends on the variables of the particular test, including pulse rate, pulse uniformity, and the thermal time constant of the calorimeter. 1.3 A determination of the dose is made directly for the material of which the calorimeter block is made. The dose in other materials can be calculated from this measured value by formulas presented in this test method. The need for such calculations and the choice of materials for which calculations are to be made shall be subject to agreement by the parties to the test. 1.4 The values stated SI units are to be regarded as the standard. The values in parenthesis are provided for information only. 1.5 This standard does not purport to address 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 Test Method for Measuring Dose for Use in Linear Accelerator Pulsed Radiation Effects Tests

ASTM F526-97(2003) 测定用于线性加速器脉冲发射效应试验的剂量的试验方法

An accurate measure of the dose during radiation-effects testing is necessary to ensure the validity of the data taken, to enable comparison to be made of data taken at different facilities, and to verify that components or circuits are tested to the radiation specification applied to the system for which they are to be used. The primary value of a calorimetric method for measuring dose is that the results are absolute. They are based only on physical properties of materials, that is, the specific heat of the calorimeter-block material and the Seebeck emf of the thermocouple used or the temperature coefficient of resistance (α) of the thermistor used, all of which can be established with non-radiation measurements. The method permits repeated measurements to be made during a radiation effects test without requiring entry into the radiation cell between measurements.1.1 This test method covers a calorimetric measurement of the dose delivered in a single pulse of electrons from an electron linear accelerator used as an ionizing source in radiation-effects testing. The test method is designed for use with pulses of electrons in the energy range from 10 to 50 MeV and is only valid for cases in which both the calorimeter and the test specimen to be irradiated are" thin" compared to the range of these electrons in the materials of which they are constructed.1.2 The procedure described can be used in those cases in which (1) the dose delivered in a single pulse is 5 Gy (500 rad) or greater, or (2) multiple pulses of a lower dose can be delivered in a time short compared to the thermal time constant of the calorimeter. The minimum dose per pulse that can be acceptably monitored depends on the variables of the particular test, including pulse rate, pulse uniformity, and the thermal time constant of the calorimeter.1.3 A determination of the dose is made directly for the material of which the calorimeter block is made. The dose in other materials can be calculated from this measured value by formulas presented in this test method. The need for such calculations and the choice of materials for which calculations are to be made shall be subject to agreement by the parties to the test.1.4 The values stated in SI units are to be regarded as the standard. The values in parenthesis are provided for information only.1.5 This standard does not purport to address 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 Measuring Dose for Use in Linear Accelerator Pulsed Radiation Effects Tests

ASTM D5403-93(2013) 辐射固化材料中挥发物含量的标准试验方法

5.1 These test methods are the procedures of choice for determining volatile content of materials designed to be cured by exposure to ultraviolet light or electron beam irradiation. These types of materials contain liquid reactants that react to become part of the film during cure, but, which under the test conditions of Test Method D2369, will be erroneously measured as volatiles. The conditions of these test methods are similar to Test Method D2369 with the inclusion of a step to cure the material prior to weight loss determination. Volatile content is determined as two separate components—processing volatiles and potential volatiles. Processing volatiles is a measure of volatile loss during the actual cure process. Potential volatiles is a measure of volatile loss that might occur during aging or under extreme storage conditions. These volatile content measurements are useful to the producer and user of a material and to environmental interests for determining emissions. 1.1 These test methods cover procedures for the determination of weight percent volatile content of coatings, inks, and adhesives designed to be cured by exposure to ultraviolet light or to a beam of accelerated electrons. 1.2 Test Method A is applicable to radiation curable materials that are essentially 1008201;% reactive but may contain traces (no more than 38201;%) of volatile materials as impurities or introduced by the inclusion of various additives. 1.3 Test Method B is applicable to all radiation curable materials but must be used for materials that contain volatile solvents intentionally introduced to control application viscosity and which are intended to be removed from the material prior to cure. 1.4 These test methods may not be applicable to radiation curable materials wherein the volatile material is water, and other procedures may be substituted by mutual consent of the producer and user. 1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.6 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. A specific hazard statement is given in 15.7.

Standard Test Methods for Volatile Content of Radiation Curable Materials