1、BSI Standards PublicationBS ISO 19017:2015Guidance for gammaspectrometry measurement ofradioactive wasteBS ISO 19017:2015 BRITISH STANDARDNational forewordThis British Standard is the UK implementation of ISO 19017:2015.It supersedes BS ISO 14850-1:2004 which is withdrawn.The UK participation in its
2、 preparation was entrusted to TechnicalCommittee NCE/9, Nuclear fuel cycle technology.A list of organizations represented on this committee can beobtained on request to its secretary.This publication does not purport to include all the necessaryprovisions of a contract. Users are responsible for its
3、 correctapplication. The British Standards Institution 2015.Published by BSI Standards Limited 2015ISBN 978 0 580 85525 2ICS 13.030.30; 17.240; 27.120.30Compliance with a British Standard cannot confer immunity fromlegal obligations.This British Standard was published under the authority of theStand
4、ards Policy and Strategy Committee on 31 December 2015.Amendments/corrigenda issued since publicationDate T e x t a f f e c t e dBS ISO 19017:2015 ISO 2015Guidance for gamma spectrometry measurement of radioactive wasteLignes directrices pour le mesurage de dchets radioactifs par spectromtrie gammaI
5、NTERNATIONAL STANDARDISO19017First edition2015-12-15Reference numberISO 19017:2015(E)BS ISO 19017:2015ISO 19017:2015(E)ii ISO 2015 All rights reservedCOPYRIGHT PROTECTED DOCUMENT ISO 2015, Published in SwitzerlandAll rights reserved. Unless otherwise specified, no part of this publication may be rep
6、roduced or utilized otherwise in any form or by any means, electronic or mechanical, including photocopying, or posting on the internet or an intranet, without prior written permission. Permission can be requested from either ISO at the address below or ISOs member body in the country of the request
7、er.ISO copyright officeCh. de Blandonnet 8 CP 401CH-1214 Vernier, Geneva, SwitzerlandTel. +41 22 749 01 11Fax +41 22 749 09 47copyrightiso.orgwww.iso.orgBS ISO 19017:2015ISO 19017:2015(E)Foreword ivIntroduction v1 Scope . 12 Terms and definitions . 13 Application . 73.1 General . 73.2 Typical applic
8、ations 74 Measurement equipment 84.1 General . 84.2 Open detector geometry . 84.3 Collimated detector geometry 104.4 Components of gamma measurement system 134.4.1 Mechanical equipment.134.4.2 Radiation detection equipment .144.4.3 Data acquisition and analysis unit .144.4.4 Electrical control .144.
9、4.5 Additional equipment .145 Calibration .145.1 General 145.2 Peak energy and shape calibration of the gamma spectrometry system 155.3 Efficiency calibration of the gamma spectrometry system .155.4 Attenuation correction techniques . 186 Data evaluation .186.1 Data processing steps. 186.2 Calculati
10、on of net peak count rates 196.3 Calculation of gamma activity inventory of the waste package .206.4 Calculation of measurement uncertainty 206.5 Calculation of detection limit. 217 Quality assurance .237.1 General 237.2 Record of calibration, validation, and waste measurements .237.3 Documentation
11、and procedures . 247.4 Quality control 247.5 Competence 25Annex A (informative) Examples of application of the techniques and methods discussed within this International Standard 26Bibliography .47 ISO 2015 All rights reserved iiiContents PageBS ISO 19017:2015ISO 19017:2015(E)ForewordISO (the Intern
12、ational Organization for Standardization) is a worldwide federation of national standards bodies (ISO member bodies). The work of preparing International Standards is normally carried out through ISO technical committees. Each member body interested in a subject for which a technical committee has b
13、een established has the right to be represented on that committee. International organizations, governmental and non-governmental, in liaison with ISO, also take part in the work. ISO collaborates closely with the International Electrotechnical Commission (IEC) on all matters of electrotechnical sta
14、ndardization.The procedures used to develop this document and those intended for its further maintenance are described in the ISO/IEC Directives, Part 1. In particular the different approval criteria needed for the different types of ISO documents should be noted. This document was drafted in accord
15、ance with the editorial rules of the ISO/IEC Directives, Part 2 (see www.iso.org/directives). Attention is drawn to the possibility that some of the elements of this document may be the subject of patent rights. ISO shall not be held responsible for identifying any or all such patent rights. Details
16、 of any patent rights identified during the development of the document will be in the Introduction and/or on the ISO list of patent declarations received (see www.iso.org/patents). Any trade name used in this document is information given for the convenience of users and does not constitute an endo
17、rsement.For an explanation on the meaning of ISO specific terms and expressions related to conformity assessment, as well as information about ISOs adherence to the WTO principles in the Technical Barriers to Trade (TBT) see the following URL: Foreword - Supplementary informationThe committee respon
18、sible for this document is ISO/TC 85, Nuclear energy, nuclear technologies, and radiological protection, Subcommittee SC 5, Nuclear fuel cycle.This first edition of ISO 19017 cancels and replaces ISO 14850-1:2006, which, in particular, did not take into account segmented measurements performed with
19、collimators, the possible use of numerical simulation for calibration and uncertainty assessment, and gamma radiation detectors other than high-purity germanium semiconductors.iv ISO 2015 All rights reservedBS ISO 19017:2015ISO 19017:2015(E)IntroductionA variety of non-destructive assay techniques a
20、re routinely used within the nuclear industry to measure or provide information to otherwise enable quantification of the radionuclide inventory of packages containing radioactive materials. This International Standard specifically considers gamma spectrometry measurements made on packages containin
21、g radioactive waste.The methods and techniques discussed within this International Standard find application in the routine assay of various types of radioactive waste, packaged in a variety of ways, employing a variety of container sizes, and types. They range from basic techniques, which have been
22、 in use for many years, through to state of the art techniques that have been developed because of the increasing variety and forms being assayed and the demands to satisfy increasingly challenging performance criteria.Where guidance is provided, this is viewed as best current practice and is based
23、on experience of operating quantitative gamma spectrometry measurement systems, within a variety of applications, for the purpose of providing radionuclide identification and activity information.The objective of this International Standard is to promote a consistent approach to gamma spectrometry m
24、easurements made on packages containing radioactive waste. ISO 2015 All rights reserved vBS ISO 19017:2015BS ISO 19017:2015Guidance for gamma spectrometry measurement of radioactive waste1 ScopeThis International Standard is applicable to gamma radiation measurements on radioactive waste.Radioactive
25、 waste can be found in different forms and exhibit a wide range of characteristics, including the following: raw or unconditioned waste, including process waste (filters, resins, control rods, scrap, etc.) and waste from dismantling or decommissioning; conditioned waste in various forms and matrices
26、 (bitumen, cement, hydraulic binder, etc.); very low level (VLLW), low level (LLW), intermediate level (ILW) and high level radioactive waste (HLW); different package shapes: cylinders, cubes, parallelepipeds, etc.Guidance is provided in respect of implementation, calibration, and quality control. T
27、he diversity of applications and system realizations (ranging from research to industrial systems, from very low level to high level radioactive waste, from small to large volume packages with different shapes, with different performance requirements and allowable measuring time) renders it impossib
28、le to provide specific guidance for all instances; the objective of this International Standard is, therefore, to establish a set of guiding principles. Ultimately, implementation is to be performed by suitably qualified and experienced persons and based on a thorough understanding of the influencin
29、g factors, contributing variables and performance requirements of the specific measurement application.This International Standard assumes that the need for the provision of such a system will have been adequately considered and that its application and performance requirements will have been adequa
30、tely defined through the use of a structured requirements capture process, such as data quality objectives (DQO).It is noted that, while outside the scope of this International Standard, many of the principles, measurement methods, and recommended practices discussed here are also equally applicable
31、 to gamma measurements of items other than radioactive waste (e.g. bulk food, water, free-standing piles of materials) or to measurements made on radioactive materials contained within non-traditional packages (e.g. in transport containers).2 Terms and definitionsFor the purposes of this document, t
32、he following terms and definitions apply.NOTE Definitions presented here are confined mainly to those terms not defined in common nuclear material glossaries or whose use is specific to this document. Important key terms are repeated here for the convenience of the reader.2.1assayprocedure to determ
33、ine quantitatively the amount of one or more radionuclides of interest contained in a packageINTERNATIONAL STANDARD ISO 19017:2015(E) ISO 2015 All rights reserved 1BS ISO 19017:2015ISO 19017:2015(E)2.2attenuationphysical process based on interaction between a radiation source and matter placed in th
34、e path of the radiation that results in a decrease in the intensity of the emitted radiationNote 1 to entry: Attenuation experienced in non-destructive assay (NDA)(2.27) of waste packages includes self-attenuation (2.37) by the radioactive material itself as well as attenuation effects in the waste
35、matrix (2.23), internal barrier(s) and external container(s).2.3attenuation correction factorused to correct (compensate) for the effect of attenuation within an NDA measurement equal to the ratio between the un-attenuated and the attenuated radiation fluxNote 1 to entry: After attenuation correctio
36、n the measured quantity is considered to be representative of the un-attenuated activity of the radioactive substance assayed.2.4biasestimate of a systematic measurement error2.5calibration standardprimary standarddesignated or widely acknowledged as having the highest metrological qualities and who
37、se value is accepted without reference to other standards of the same quantityNote 1 to entry: The calibration standard should be physically, radiologically, and chemically similar to the items to be assayed, for which the activity of the radionuclide(s) of interest and all relevant properties to wh
38、ich the measurement technique is sensitive are known with sufficient accuracy.SOURCE: www.french-2.6calibrationset of operations that establish, under specific conditions, the relationship between values of quantities indicated by a measuring system, or values represented by a material measure or a
39、reference material and the corresponding values realized by StandardsNote 1 to entry: The result of a calibration permits either the assignment of values of measurands to the indications or the determination of indications with respect to indications.Note 2 to entry: A calibration may also determine
40、 other metrological properties such as the effect of influence quantities.Note 3 to entry: The result of a calibration may be recorded in a document, sometimes called a calibration certificate or a calibration report.SOURCE: www.french-2.7collimationmethod to restrict the field of view of the detect
41、or to specific parts of the item to be measuredNote 1 to entry: A shield around the side of the detector that still allows the detector to view the entire item is technically not a collimator. Such shielding does not change the efficiency of the detector due to its presence.2.8collimatordevice for c
42、ollimating the radiation beam, usually constructed from highly attenuating material(s) such as tungsten or lead. Collimators can be of parallel wall type or divergent2 ISO 2015 All rights reservedBS ISO 19017:2015ISO 19017:2015(E)2.9collimated (detection) geometrymeasurement configuration where only
43、 a part of a waste package can contribute to the response of the detection systemNote 1 to entry: The whole activity is measured by scanning the entire package, or by assuming that the part of the package within the detectors field of view during one or more measurements is representative of the ent
44、ire package.2.10compton continuumcontinuous pulse amplitude spectrum due to Compton electrons released in a detectorNote 1 to entry: The full-energy peaks are superimposed to this continuum and their “net areas” are determined by subtracting the average Compton level estimated below each peak, as de
45、tailed in ISO 11929 for instance.SOURCE: IEC 60050-395:20142.11containervessel into which the waste form (2.41) is placed for handling, transport, storage and/or eventual disposalNote 1 to entry: Also the outer barrier protecting the waste from external intrusions.SOURCE: IAEA Radioactive Waste Mana
46、gement Glossary 2003 Edition2.12coverage factoralthough the combined standard deviation is used to express the uncertainty of many measurement results, for some commercial, industrial, and regulatory applications (e.g. when health and safety are concerned), what is often required is a measure of unc
47、ertainty that defines an interval about the measurement result within which the value of the measurand can be confidently asserted to lieNote 1 to entry: The measure of uncertainty intended to meet this requirement is termed expanded uncertainty and is obtained by multiplying the standard deviation
48、by a coverage factor, suggested symbol k. In general, the value of the coverage factor k is chosen on the basis of the desired level of confidence to be associated with the interval within which the true value is supposed to lie.SOURCE: http:/physics.nist.gov/cuu/Uncertainty/coverage.html2.13data qu
49、ality objectives processDQOseven stage requirements capture process used to determine the type, quantity, and quality of data needed to support a decisionNote 1 to entry: The purpose of this process (published by the US Environmental Protection Agency) is to provide general guidance to organizations on developing data quality criteria and performance specifications for decision making.2.14dead timenon-operative time of the detection system during the measurement periodNote 1 to entry: The length of time, directly followin
