17.240 辐射测量 标准查询与下载



共找到 1731 条与 辐射测量 相关的标准,共 116

Guide for estimating uncertainties in dosimetry for radiation processing

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20220711
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20220711

Reference radiation fields-Simulated workplace neutron fields-Part 1:Characteristics and methods of production

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20220711
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20220711

Reference neutron radiations-Part 2:Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field

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20220711
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20220711

Reference radiation fields-Simulated workplace neutron fields-Part 2:Calibration fundamentals related to the basic quantities

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17.240
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20220711
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20220711

Practice for dosimetry in a gamma irradiation facility for radiation processing

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20220711
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20220711

Guide for use of radiation-sensitive indicators

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20220711
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20220711

Radiation protection-Criteria and performance limits for the periodic evaluation of processors of personal dosemeters for X and gamma radiation

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20220711
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20220711

Reference neutron radiations-Characteristics and methods of production of simulated workplace neutron fields

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20220711
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20220711

Measurements of the electrical properties of electronic tubes-Methods of measurement of Geiger-Müller counter tubes

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17.240
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20220711
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20220711

Practice for dosimetry in an X-ray (bremsstrahlung) facility for radiation processing

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17.240
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20220711
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20220711

Reference neutron radiations-Characteristics and methods of production

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17.240
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20220711
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20220711

Nuclear instrumentation — Measurement of gamma-ray emission rates of radionuclides — Calibration and use of germanium spectrometers

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17.240
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发布
20220711
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20220711

1.1 This test method covers a general procedure for the measurement of the fast-neutron fluence rate produced by neutron generators utilizing the 3 H(d,n)4 He reaction. Neutrons so produced are usually referred to as 14-MeV neutrons, but range in energy depending on a number of factors. This test method does not adequately cover fusion sources where the velocity of the plasma may be an important consideration. 1.2 This test method uses threshold activation reactions to determine the average energy of the neutrons and the neutron fluence at that energy. At least three activities, chosen from an appropriate set of dosimetry reactions, are required to characterize the average energy and fluence. The required activities are typically measured by gamma-ray spectroscopy. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Test Method for Measuring Neutron Fluence and Average Energy from 3H(d,n)4He Neutron Generators by Radioactivation Techniques

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17.240
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2022-07-01
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1.1 This test method covers procedures for measuring reaction rates by the activation reaction nat Ti(n,X)46 Sc. The “X” designation represents any combination of light particles associated with the production of the residual 46 Sc product. Within the applicable neutron energy range for fission reactor applications, this reaction is a properly normalized combination of three different reaction channels: 46 Ti(n,p)46 Sc; 47 Ti(n, np)46 Sc; and 47 Ti(n,d)46 Sc. NOTE 1—The 47 Ti(n,np)46 Sc reaction, ENDF-6 format file/reaction identifier MF=3, MT=28, is distinguished from the 47 Ti(n,d)46 Sc reaction, ENDF-6 format file/reaction identifier MF=3/MT=104, even though it leads to the same residual product (1).2 The combined reaction, in the IRDFF-II library, has the file/reaction identifier MF=10/MT=5. NOTE 2—The cross section for the combined 47 Ti(n,np:d) reaction is relatively small for energies less than 12 MeV and, in fission reactor spectra, the production of the residual 46 Sc is not easily distinguished from that due to the 46 Ti(n,p) reaction. 1.2 The reaction is useful for measuring neutrons with energies above approximately 4.4 MeV and for irradiation times, under uniform power, up to about 250 days (for longer irradiations, or for varying power levels, see Practice E261). 1.3 With suitable techniques, fission-neutron fluence rates above 109 cm–2 ·s–1 can be determined. However, in the presence of a high thermal-neutron fluence rate, 46 Sc depletion should be investigated. 1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E261. 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 concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Test Method for Measuring Fast-Neutron Reaction Rates By Radioactivation of Titanium

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17.240
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发布
2022-07-01
实施

本文件规定了输电线路导线压接X射线数字成像无损检测作业的术语和定义、总则、检测设备、辐射防护、登高作业、检测方法、成像要求、记录及报告等要求。 本文件适用于输电线路导(地)线耐张线夹和接续管压接质量的X 射线数字成像无损检测现场作业。

Operation guideline for crimping X-ray digital imaging non-destructive testing of conductors of transmission lines

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17.240
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D4420
发布
2022-06-23
实施
2022-10-01

This document addresses aspects of management of solid biomedical radioactive waste from its generation in nuclear medicine facilities to final clearance and disposal, as well as the manner to establish an effective program for biomedical radioactive waste management. Liquid and gaseous wastes are excluded from the scope of the document, but solid waste includes spent and surplus solutions of radionuclides contained in vials, tubes or syringes. Therefore, this document should be useful for any nuclear medicine facilities dealing with in vivo medical applications of radionuclides and consequently with the waste associated with such applications. This document provides a list of the main radionuclides used in nuclear medicine facilities and their main physical characteristics, as well as the guidance to write a radioactive waste management program for their sorting, collection, packaging and labelling, radioactivity surveys and decay storage, clearance levels, and transportation, if necessary, until their ultimate disposal or discharge. This document may also be useful as guidance for regulatory bodies.

Radiological protection — Measurement for the clearance of waste contaminated with radioisotopes for medical application — Part 2: Management of solid radioactive waste in nuclear medicine facilities

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发布
2022-06-21
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Measurement of radioactivity — Gamma emitting radionuclides — Reference measurement standard specifications for the calibration of gamma-ray spectrometers

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发布
2022-05-25
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Practice for use of a radiochromic optical waveguide dosimetry system

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发布
2022-04-26
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What is ISO 8529-1 about?    ISO 8529-1 is the first of a set of three International Standards concerning the calibration of dosemeters and dose rate meters for neutron radiation for protection purposes.   ISO 8529-1 is the first part in a multi-series that specifies the neutron reference radiation fields, in the energy range from thermal up to 20 MeV, for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response as a function of neutron energy.    The neutron reference radiation fields specified are the following:   Neutron fields from radionuclide sources, including neutron fields from sources in a moderator

Neutron reference radiations fields. Characteristics and methods of production

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17.240
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发布
2021-12-31
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2021-12-31

1.1 This guide provides techniques that can be used to ensure the proper operation and use of Hazardous Material detection equipment. This document cannot replace education or experience and should be used in conjunction with professional judgment. Not all aspects of this guide may be applicable in all circumstances. 1.2 This guide is not intended to represent or replace any accreditation or certification documents by which the adequacy of a given professional service must be judged. 1.3 This guide 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 guide to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. 1.4 When using HAZMAT equipment follow the manufacturer’s guidance and appropriate safety practices for the expected or suspected threat. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Guide for Acquisition, Maintenance, Storage, and Use of Hazardous Material Detection Instrumentation

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17.240
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发布
2021-12-15
实施



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