F73 环境辐射防护与核医学防护 标准查询与下载

ASTM C852-09 防钚辐射手套箱设计准则的标准指南

The purpose of this guide is to establish criteria for the design of gloveboxes as primary confinement systems to ensure the safety of the workers and the protection of the environment when storing, handling, processing, and disposing of both combustible and non-combustible forms of plutonium. The use of this standard will provide the user with guidance to design a successfully performing glovebox system.1.1 This guide defines criteria for the design of glovebox systems to be used for the handling of plutonium in any chemical or physical form or isotopic composition or when mixed with other elements or compounds. Not included in the criteria are systems auxiliary to the glovebox systems such as utilities, ventilation, alarm, and waste disposal. Also not addressed are hot cells or open-face hoods. The scope of this guide excludes specific license requirements relating to provisions for criticality prevention, hazards control, safeguards, packaging, and material handling. Observance of this guide does not relieve the user of the obligation to conform to all federal, state, and local regulations for design and construction of glovebox systems. 1.2 The values stated in SI 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 establilsh appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Design Criteria for Plutonium Gloveboxes

GOST R IEC/TR 61948-2-2008 核医学仪器. 常规试验. 第2部分. 闪烁照相机和单光子发射计算机断层成像

Nuclear medicine instrumentation. Routine tests. Part 2. Scintillation cameras and single photon emission computed tomography imaging

EJ/T 1203-2006 核设施退役实施中辐射防护大纲要求

本标准规定了核设施退役实施中辐射防护大纲应包含的基本要素及其要求。 本标准规定了核设施退役实施中辐射防护大纲的编写和实施。

Requirements of radiation protection program for decommissioning operations of nuclear facilities

EJ/T 1191-2005 推导退役后场址土壤中放射性残存物可接受活度浓度的照射情景、计算模式和参数

本标准规定了推导退役后场址土壤中放射性残存物可接受活度浓度的环境照射情景、照射途径、计算模式和主要参数。 本标准适用于退役后拟开放场址土壤中放射性残存物可接受活度浓度的确定。

Exposure scenarios, calculation models and parameters for driving acceptable levels of residual radioactive materials left in soil of a site following decommissioning

EJ 1186-2005 放射性废物体和废物包的特性鉴定

本标准规定了各种放射性废物体和废物包的性能要求及其检验方法，包括取样方法、数据处理方法和质量保证的一般要求。 本标准适用于核设施运行、退役和其他核活动产生的放射性废物体和废物包。 本标准不适用于乏燃料运输货包。

Characterization of radioactive waste forms and packages

ANSI/ASME AG-1a-2004 核气体和气体处理法规

Provides requirements for design, fabrication, inspection, and testing of air cleaning and conditioning components and appurtenances, as well as air cleaning components used in engineering safety systems in nuclear facilities.

Code on Nuclear Air and Gas Treatment

ASTM C1379-04 用感应耦合等离子体质谱法分析铀235和铀238同位素用尿的标准试验方法

DOE Order 5480.11 and ANSI N13.30 require that internal dose assessments be made as part of the bioassay program for nuclear facility workers. For indirect bioassay of uranium workers, the uranium isotopes must be measured along with the total uranium in urine samples. The RMDA for each uranium isotope is 0.1 pCi/L. This method is applicable for measuring 235U and 238U at the RMDA. Because of extremely low mass concentration (because of the high specific activity), 234U cannot be measured without additional sample preconcentration. Note 28212;Column chromatography separations and concentration of 234U using manual or flow-injection preconcentration followed by ICP-MS isotopic determination are described in Test Methods C 1310 and C 1345. These methods focus on environmental soil sample analysis, but with some development, may be applicable to digested urine samples. The 234U concentration can be calculated based on an enrichment gradient for workers in uranium enrichment plants, and internal dose assessments can be made. Note 38212;Use of high resolution ICP-MS may also be used to obtain lower detection limits, see 1.1.1 This test method covers the determination of the concentration of uranium-235 and uranium-238 in urine using Inductively Coupled Plasma-Mass Spectrometry. This test method can be used to support uranium facility bioassay programs.1.2 This method detection limits for 235U and 238U are 6 ng/L. To meet the requirements of ANSI N13.30, the minimum detectable activity (MDA) of each radionuclide measured must be at least 0.1 pCi/L (0.0037 Bq/L). The MDA translates to 47 ng/L for 235U and 300 ng/L for 238U. Uranium- 234 cannot be determined at the MDA with this test method because of its low mass concentration level equivalent to 0.1 pCi/L. 1.3 The digestion and anion separation of urine may not be necessary when uranium concentrations of more than 100 ng/L are present.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.The ICP-MS is a source of intense ultraviolet radiation from the radio frequency induced plasma. Protection from radio frequency radiation and UV radiation is provided by the instrument under normal operation.

Standard Test Method for Analysis of Urine for Uranium-235 and Uranium-238 Isotopes by Inductively Coupled Plasma-Mass Spectrometry

ISO 12794:2000 核能 辐射防护 肢端和眼睛个人热释光剂量计

This International Standard provides performance criteria and tests for determining the performance of thermoluminescence dosemeters intended to be used for the measurement of radiation doses to the eyes and extremities (fingers, and limbs defined as hands, feet, forearms including the elbow, and leg including the patella), for photons from 15keV to 3 MeV and beta radiation from 0,5 MeV to 3 MeV. It is conditional upon the use of an appropriate reader, procedures and ancillary equipment. It does not cover information access and data processing. This International Standard provides performance criteria and tests for dosemeters intended to measure dose equivalent at depths of 7 mg·cm in tissue for fingers and limbs and 300 mg·cm in tissue for the eyes, including provision for the use of dosemeters only intended to be used once. Appropriate phantoms and dose conversion coefficients are recommended but others are not precluded. In all cases, performance is assessed under laboratory conditions which may not adequately simulate conditions actually experienced in personal dosimetry. For example, it may be necessary to sterilize dosemeters for medical applications. Therefore, caution is necessary in applying the results of these performance tests in real situations.

Nuclear energy - Radiation protection - Individual thermoluminescence dosemeters for extremities and eyes

NF M60-703:1998 表面污染的评估.第3部分:同质异能跃迁和电子俘获发射器，低能量β发射器(Eβ最大值不超过0,15MEV)

Evaluation of surface contamination. Part 3 : isomeric transition and electron capture emitters, low energy beta-emitters (E beta max inferior to 0,15 MeV).

NF M60-764:1997 核能.环境空气放射性的空气测量.Radon 222 : 大气环境中氡的短寿命衰变产品的α位能的综合测量方法

Nuclear energy. Air-Measurement of radioactivity in the environment-Air. Radon 222 : integrated methods for measurement of alpha potential energy of short life decay products of radon in the atmospheric environment.

NF M60-765:1997 核能.环境空气放射性的空气测量. Radon 222:大气环境氡裂变产物的α位能的点测量方法

Nuclear energy. Air-measurement of radioactivity in the environment. Radon 222 : methods for spot measurement of alpha potential energy of radon daughters in the atmospheric environment.

NF M60-800:1997 核能.环境放射性测量.水.低盐水中根据锶和钇90当量测量总β放射性指数

Nuclear energy. Measurement of environmental radioactivity. Water. Measurement of global beta activity index in terms of strontrium and yttrium 90 equivalent in low salted water.

NF M60-801:1997 核能.环境放射性测量.水.低盐水中根据钚239当量测量α放射性指数

Nuclear energy. Measurement of environmental radioactivity. Water. Measurement of alpha activity index in terms of plutonium 239 equivalent in low salted water.

NF M60-780-3:1997 核能.环境中放射性测量.生物指示器.第3部分:样品的储存和运输通用指南

Nuclear energy. Measurement of radioactivity in the environment. Bioindicators. Part 3 : general guide for the storage and handling of samples.

ASTM C1379-97 用电感耦合的等离子质谱法对铀235和铀238同位素进行尿分析的标准试验方法

1.1 This test method covers the determination of the concentration of uranium-235 and uranium-238 in urine using Inductively Coupled Plasma-Mass Spectrometry. This test method can be used to support uranium facility bioassay programs. 1.2 The method detection limits for 235U and 238U are 6 ng/L. To meet the requirements of ANSI N13.30, the minimum detectable activity (MDA) of each radionuclide measured must be at least 0.1 pCi/L (0.0037 Bq/L). The MDA translates to 47 ng/L for 235U and 300 ng/L for 238U. Uranium-234 cannot be determined at the MDA with this test method because of its low mass concentration level equivalent to 0.1 pCi/L. 1.3 The digestion and anion separation of urine may not be necessary when uranium concentration of 062100 ng/L U are present. Note 1: Warning--The ICP-MS is a source of intense ultraviolet radiation from the radio frequency induced plasma. Protection from radio frequency radiation and UV radiation is provided by the instrument under normal operation. 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 Test Method for Analysis of Urine for Uranium-235 and Uranium-238 Isotopes by Inductively Coupled Plasma-Mass Spectrometry

WS/T 74-1996 医学放射工作人员的放射防护培训规范

本标准规定了医学放射工作人员放射防护培训的宗旨、对象、内容、方式、考核及实施等基本要求。 本标准适用于一切从事电离辐射医学应用工作人员的放射防护培训。

Regulation of radiological protection training for the medical radiation workers

EJ/T 968-1995 生产堆退役环境和流出物辐射监测准则

本标准规定了生产堆退役环境辐射监测和流出物辐射监测的基本要求、监测项目、监测技术及监测结果的分析。 本标准适用于我国生产堆不同退役阶段中环境和流出物的辐射监测。

Guidelines for Environmental and Effluent Radiation Monitoring of Production Reactor Decommissioning

ASTM E1168-95e1 核设施工人辐射防护训练

1.1 This guide covers general recommendations with respect to standard work practices, procedures, and measurement methods for the radiological protection portion of health and safety training for radiation workers at nuclear facilities. This guide defines the elements of a training program for radiation workers consistent with the philosophy that occupational radiation exposure be kept as low as is reasonably achievable (ALARA). Regulatory agencies have statutory responsibilities to promulgate regulations applying to the training of workers exposed to radiation hazards. This guide shall not take precedence over any such regulations.1.2 This guide is intended to help ensure that the employer provides the radiation worker with radiological protection training that the worker needs to work safely in a radiologically controlled area and to maintain radiation exposure ALARA.1.3 The scope of radiological protection training shall be related to the duties and responsibilities of each radiation worker and shall be commensurate with potential radiological protection problems in the radiologically controlled area.1.4 This guide is also intended to provide guidance that will enable an evaluation of the effectiveness of the radiological protection training program toward achieving the purpose stated in Section 4.1.5 This guide does not cover the more detailed training requirements for radiation protection professionals or technicians.1.6 This guide provides reference to the type of radiological protecting training records that should be created, and recommends retention periods for radiological protection training records.1.7 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 Radiological Protection Training for Nuclear Facility Workers

ASTM E1168-95(2001) 核设施工人辐射防护训练

1.1 This guide covers general recommendations with respect to standard work practices, procedures, and measurement methods for the radiological protection portion of health and safety training for radiation workers at nuclear facilities. This guide defines the elements of a training program for radiation workers consistent with the philosophy that occupational radiation exposure be kept as low as is reasonably achievable (ALARA). Regulatory agencies have statutory responsibilities to promulgate regulations applying to the training of workers exposed to radiation hazards. This guide shall not take precedence over any such regulations.1.2 This guide is intended to help ensure that the employer provides the radiation worker with radiological protection training that the worker needs to work safely in a radiologically controlled area and to maintain radiation exposure ALARA.1.3 The scope of radiological protection training shall be related to the duties and responsibilities of each radiation worker and shall be commensurate with potential radiological protection problems in the radiologically controlled area.1.4 This guide is also intended to provide guidance that will enable an evaluation of the effectiveness of the radiological protection training program toward achieving the purpose stated in Section 4.1.5 This guide does not cover the more detailed training requirements for radiation protection professionals or technicians.1.6 This guide provides reference to the type of radiological protecting training records that should be created, and recommends retention periods for radiological protection training records.1.7 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 Radiological Protection Training for Nuclear Facility Workers

ASTM E1168-95(2008) 核设施工人辐射防护训练的标准指南

The purpose of this guide is to define the elements of a radiological protection training program that will enable a radiation worker, upon completion of training, to achieve the following: 4.1.1 Understand the relative health and safety risks associated with the types and levels of radiation that may be encountered during the work assignment in radiologically controlled areas, 4.1.2 Complete the forms and records necessary to be permitted to function as a radiation worker, 4.1.3 Practice the necessary monitoring and contamination control techniques to minimize exposure to radiation or radioactive materials, or both, and 4.1.4 Practice work habits that will minimize the impact of radiation or radioactive materials, or both, upon the workplace and surrounding environments. The standardization of radiation worker radiological protection training provides the individual radiation worker with a greater assurance that the training received is adequate to minimize radiation exposure, to enable the worker to work safely in a radiologically controlled area, and to meet applicable regulations. The standardization of radiation worker radiological protection training prevents unnecessary retraining of radiation workers. This guide should be used as the basis for establishing a radiological protection training program for radiation workers at nuclear facilities.1.1 This guide covers general recommendations with respect to standard work practices, procedures, and measurement methods for the radiological protection portion of health and safety training for radiation workers at nuclear facilities. This guide defines the elements of a training program for radiation workers consistent with the philosophy that occupational radiation exposure be kept as low as is reasonably achievable (ALARA). Regulatory agencies have statutory responsibilities to promulgate regulations applying to the training of workers exposed to radiation hazards. This guide shall not take precedence over any such regulations. 1.2 This guide is intended to help ensure that the employer provides the radiation worker with radiological protection training that the worker needs to work safely in a radiologically controlled area and to maintain radiation exposure ALARA. 1.3 The scope of radiological protection training shall be related to the duties and responsibilities of each radiation worker and shall be commensurate with potential radiological protection problems in the radiologically controlled area. 1.4 This guide is also intended to provide guidance that will enable an evaluation of the effectiveness of the radiological protection training program toward achieving the purpose stated in Section 4. 1.5 This guide does not cover the more detailed training requirements for radiation protection professionals or technicians. 1.6 This guide provides reference to the type of radiological protecting training records that should be created, and recommends retention periods for radiological protection training records. 1.7 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 Radiological Protection Training for Nuclear Facility Workers