F72 核设施的辐射安全 标准查询与下载

ANSI/ANS 15.11-2009 研究反应堆设施辐射的防护

This standard establishes the element of a radiation protection program and the criteria necessary to provide an acceptable level of radiation protection for personnel at research reactor facilities and the public consistent with keeping exposures and releases as low as reasonably achievable (ALARA).

Radiation Protection at Research Reactors

EJ 993-2008 铀矿冶辐射防护规定

本标准规定了铀矿山和选冶厂的选址、设计、建设、运行、关闭和退役等辐射防护原则和基本要求。 本标准适用于铀矿山和铀选冶厂。含有铀钍元素伴生矿的矿山或选冶厂亦可参照执行。

Regulation for the radiation protection of uranium mine and mill

EJ/T 359-2006 铀矿井排氡及通风技术规范

本标准规定了铀矿井通风与排氡的基本原则、技术要求和风量计算方法，给出了通风控制铀矿井氡所致辐射危害的措施及技术规范。 本标准适用于新建、改建、扩建和生产铀矿井的通风设计和通风管理。存在氡所致辐射危害的非铀矿井和地下工程，可以参照执行。

Technical regulations for radon exhaustion and ventilation in underground uranium mine

EJ/T 270-2005 核电厂运行辐射防护规定

本标准规定了核电厂运行期间工作人员辐射防护的基本要求。 本标准适用于陆上固定式水冷反应堆核电厂装载核燃料后的调试、运行以及检查、试验、维修、电厂改造和放射性废物管理等生产活动及核事故应急响应中工作人员的照射控制。核电厂厂址选择、设计、建造和退役可参照使用。

Rules for operational radiation protection in nuclear power plants

ASTM E2421-05 停运核设施用废弃物管理规划的制定的标准指南

A waste management plan based on the contents of this guide will provide for the successful identification of potential waste streams anticipated from decommissioning activities, and provide a clear and concise methodology for the handling of identified waste from generation to final disposition. The waste management plan will identify the general waste types, characterization, packaging, transportation, disposal, and quality assurance requirements for potential waste streams.1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal.1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations.1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams.1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams.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 Preparing Waste Management Plans for Decommissioning Nuclear Facilities

ASTM D7108-05 确立核涂层专家资格的标准指南

This guide applies to personnel technically responsible for the safety-related coatings program. It is the responsibility of each nuclear facility or organization participating in a safety-related coatings program to ensure that only those personnel within their respective organizations who meet the requirements of this guide are designated as Nuclear Coatings Specialists.1.1 This guide delineates recommendations for development of procedures and criteria for designation of personnel as a Nuclear Coatings Specialist involved in work in nuclear facilities. The Nuclear Coatings Specialist is responsible for the technical aspects of the safety-related coatings program in a nuclear facility or organization.1.2 This guide details the guidance provided in Guide D 5144, USNRC Regulatory Guide 1.54 Revision 1, and EPRI Report 1003102.1.3 It is the intent of this guide to provide several alternatives for designation of personnel as Nuclear Coatings Specialists.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 requirements prior to use.

Standard Guide for Establishing Qualifications for a Nuclear Coatings Specialist

EJ/T 1172-2004 核电厂高和超高辐射区的进入控制

本标准规定了核电厂高和超高辐射区的确定原则和人员进入的控制措施。 本标准适用于运行中的核电厂，退役核电厂和其它核设施的高和超高辐射区的进入控制原则上也可 参考本标准的规定。

Control of access to high and super-high radiation areas in nuclear power plant

ANSI N13.36-2001 工作人员离子辐射安全培训

Establishes minimum requirements and provides recommendations and guidelines for the analysis, design, development, implementation, and evaluation of ionizing radiation safety training for workers. Target audience, responsibilities, training topics, and

Ionizing Radiation Safety Training for Workers

ANSI N13.39-2001 内部放射量测定计划设计

Contains the essential elements of the internal dosimetry component of a radiation protection program. It provides general policies and the framework for the design and implementation of an acceptable internal dosimetry program.

Design of Internal Dosimetry Programs

DIN 25420-3 Bb.1:2000 混凝土热室的建造.第3部分:对于不同密度混凝土墙上辐射防护窗的要求.安装导则

Construction of concrete hot cells - Part 3: Requirements for shielding windows for concrete walls with different densities; installation guidelines

DIN 25420-4:2000 混凝土热室的建造.第4部分:对密度为2.3g/cm3的不同厚度混凝土墙上辐射防护窗的要求

The document specifies requirements relating to shielding windows for shielding walls against ionizing radiation. The shielding walls form part of the basic equipment of hot cells for remote handling. It specifies some types of shielding windows for walls with densities of concrete of 2,3 g/cm and differing thickness. It servers to define requirements relating to manufacturing, dealing especially with main dimensions, through-visibility, shielding properties and resistance to radiation.

Construction of concrete hot cells - Part 4: Requirements of shielding windows for concrete walls density 2,3 g/cm<(hoch)3> with different thicknesses

DIN 25420-3:2000 混凝土热室的建造.第3部分:对于不同密度混凝土墙上辐射防护窗的要求

The document specifies requirements relating to shielding windows for shielding walls against ionizing radiation. These shielding windows form part of the basic equipment of hot cells for remote handling complying with DIN 25420-1. In addition they can also be used in concrete walls with thickness deviating from the standard dimensions as specified in DIN 25420-2. It serves to define requirements relating to manufacturing, dealing especially with main dimensions, through-visibility, shielding properties and resistance to radiation.#,,#

Construction of concrete hot cells - Part 3: Requirements for shielding windows for concrete walls with different densities

EJ 556-1999 核安全与辐射安全文件格式与内容标准的编制规定

Drafting rules for format and content standard of nuclear and radiation safety document

JIS Z 4819:1995 辐射防护屏蔽垫

この規格は，x線，γ線の遮へい具として使用する放射線遮へいマット(以下，マットという。)について規定する。

Radiation shielding mats

JIS Z 4817:1995 辐射防护屏蔽铅砖

この規格は，原予力関連の事業所において。放射性同位元素，放射線発生装置などを使用するとき，X線，γ線などを遮へいするために用いる放射線遮へい川鉛ブロック(以下，鉛ブロックという。)について規定する。

Radiation shielding lead bricks

ASTM E1034-95(2013) 核设施工人瞬时记录的标准规范

4.1 The standardization of nuclear facility transient worker records will provide the individual transient worker with a greater assurance that the radiation doses that may be received are within regulatory limits. 4.2 This specification establishes a fixed content for nuclear facility transient worker records. Standardizing the content of these records will facilitate interfacing with industry-wide record keeping systems, such as the Nuclear Energy Institute (NEI) Personnel Data System (PADS). 4.3 The standardization of nuclear facility transient worker records will reduce the time required for in-processing of these workers. 1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. 1.2 This specification applies to records to be used for in-processing only. 1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications). 1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1???Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction does not alter the required content of records needed for in-processing of nuclear facility transient workers. Note 2???This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).

Standard Specification for Nuclear Facility Transient Worker Records

ASTM E1168-95(2013) 核设施工人放射性防护培训的标准指南

4.1 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. 4.2 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. 4.3 The standardization of radiation worker radiological protection training prevents unnecessary retraining of radiation workers. 4.4 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.

Standard Guide for Radiological Protection Training for Nuclear Facility Workers

DIN 25407 Bb.1:1994 防电离放射屏蔽墙.铅制砖墙构筑的推荐标准

Shielding walls against ionizing radiation - Recommendations for the construction of walls made of lead bricks

EJ/T 849-1994 核燃料后处理厂辐射安全设计规定

Regulations on Radiation Safety Design of Nuclear Fuel Reprocessing Plants

EJ/T 794-1993 铀水冶厂尾矿库安全设计规定

Regulations on Safety Design of Tailings Pool in Uranium Hydrometallurgy Plant