F70 辐射防护与监测综合 标准查询与下载



共找到 170 条与 辐射防护与监测综合 相关的标准,共 12

1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations.1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project.1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan.1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of the general public and the environment by describing the basic elements of a radiation protection program for decommissioning operations.1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of a decommissioning activity are attained within the radiological limits and restrictions imposed by applicable governing and regulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment. This guide should be used for developing the documentation that defines the intent and implementation of the radiation protection program for a specific decommissioning project.1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed and maintained such that it satisfies all applicable Quality Assurance requirements developed for the decommissioning project. Note 18212;If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in the development of the Radiation Protection Program for the decommissioning site.1.7 This guide does not address the subjects of emergency preparedness, safeguards, accountability, waste handling, storage, and transportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes a program in and of itself from program definition through implementation.1.8 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 Radiation Protection Program for Decommissioning Operations

ICS
13.280 (Radiation protection); 27.120.10 (Reactor
CCS
F70
发布
1987
实施

A program based on this guide will provide assurance to all concerned that the appropriate elements of radiation safety have been included to protect workers, the general public, and the environment in proximity to the decommissioning activities. Implementation of such a program will provide assurance to those agencies responsible for review or audit of the decommissioning project that the requirements for radiation protection have been addressed. RADIATION PROTECTION PROGRAM Top 1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations. 1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project. 1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan. 1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of the general public and the environment by describing the basic elements of a radiation protection program for decommissioning operations. 1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of a decommissioning activity are attained within the radiological limits and restrictions imposed by applicable governing and regulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment. This guide should be used for developing the documentation that defines the intent and implementation of the radiation protection program for a specific decommissioning project. 1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed and maintained such that it satisfies all applicable Quality Assurance requirements developed for the decommissioning project. Note 18212;If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in the development of the Radiation Protection Program for the decommissioning site. 1.7 This guide does not address the subjects of emergency preparedness, safeguards, accountability, waste handling, storage, and transportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes a program in and of itself from program definition through implementation. 1.8 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 Radiation Protection Program for Decommissioning Operations

ICS
27.120.10 (Reactor engineering)
CCS
F70
发布
1987
实施

This standard deals with the construction (equipment-) quality, installation and inspection of the reactor protection system and its components. It gives a compilation of design criteria, requirements for quality and quality assurance and requirements for the functioning of the reactor protection system.; This standard gives basic requriements for recording equipment, alarm systems, status limitators and aggregate protection systems, the signals of which have priority over the signals of the reactor protection system.#,,#

Reactor protection system and monitoring equipment of the safety system

ICS
27.120.20
CCS
F70
发布
1986-11
实施

Improper closure of intermediate container Visual

RADIOACTIVE SOURCE, COBALT 60, GAMMA, M1A1

ICS
13.280
CCS
F70
发布
1986
实施

This standard defines general ratings, tests, radiation characteristics, electrical and mechanical safety and environmental ratings as well as type certification for radiation protection equipment and test set-ups.#,,#

Radiation protection equipment for the measuring and monitoring of airborne tritium; IEC 60710, edition 1981 modified

ICS
13.280
CCS
F70
发布
1985-07-01
实施

この規格は,X線装置及び映像装置(X線フィルム,増感紙など)の変調度伝達関数(以下,MTFという。)を測定するときに用いるx線吸収休(以下,吸収体という。)を材料とするx線MTF測定用デストチャート(以下,テストチャートという。)について規定する。ただし,このテストチャートで測定し,得られるのは,方形彼MTFであり,正弦波MTFを求めるには換算を必要とする。

Test charts for modulation transfer function of X-ray equipment

ICS
11.040.50
CCS
F70
发布
1984-03-01
实施

The definitions of 40 ionizing radiation terms in this standard are based upon the corresponding definitions given by the International Commission on Radiation Units and Measurements in their Report 33 (Radiation Quantities and Units). These new definito

Terminology, quantities and units concerning radiation

ICS
01.040.13;13.280
CCS
F70
发布
1983
实施
2007-02-17

Design of Gas-filled Double-bend Ducts in Concrete Shields against Gamma Radiation; Terms and Conditions

ICS
27.120.10
CCS
F70
发布
1977-10
实施

This commercial item description covers brown kraft paper used for general wrapping applications.

RADIOACTIVE SOURCE, COBALT 60, GAMMA, M1A1

ICS
13.280
CCS
F70
发布
1971-01-20
实施

本标准规定了核电厂工作人员个人监测和工作场所辐射监测的要求,包括监测内容、监测要求、监测方法和监测结果的解释、质量保证和记录保存要求。 本标准适用于核电厂正常运行及检修时的工作人员和工作场所辐射监测。 核电厂以外的其它核反应堆运行单位可参照执行。

Individual monitoring and workplace monitoring of nuclear power plant

ICS
27.130.30
CCS
F70
发布
实施
0000-00-00



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