EN ISO 19017-2017 en Guidance for gamma spectrometry measurement of radioactive waste.pdf

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1、BSI Standards PublicationWB11885_BSI_StandardCovs_2013_AW.indd 1 15/05/2013 15:06Guidance for gamma spectrometry measurement of radioactive waste (ISO 19017:2015)BS EN ISO 19017:2017EUROPEAN STANDARD NORME EUROPENNE EUROPISCHE NORM EN ISO 19017 October 2017 ICS 17.240; 27.120.30 English Version Guid

2、ance for gamma spectrometry measurement of radioactive waste (ISO 19017:2015) Lignes directrices pour le mesurage de dchets radioactifs par spectromtrie gamma (ISO 19017:2015) Leitfaden fr gammaspektrometrische Messungen von radioaktivem Abfall (ISO 19017:2015) This European Standard was approved by

3、 CEN on 13 September 2017. CEN members are bound to comply with the CEN/CENELEC Internal Regulations which stipulate the conditions for giving this European Standard the status of a national standard without any alteration. Up-to-date lists and bibliographical references concerning such national sta

4、ndards may be obtained on application to the CEN-CENELEC Management Centre or to any CEN member. This European Standard exists in three official versions (English, French, German). A version in any other language made by translation under the responsibility of a CEN member into its own language and

5、notified to the CEN-CENELEC Management Centre has the same status as the official versions. CEN members are the national standards bodies of Austria, Belgium, Bulgaria, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, Former Yugoslav Republic of Macedonia, France, Germany, Greece, Hungary

6、, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and United Kingdom. EUROPEAN COMMITTEE FOR STANDARDIZATION COMIT EUROPEN DE NORMALISATION EUROPISCHES KOMITEE FR NORMUNG CEN

7、-CENELEC Management Centre: Avenue Marnix 17, B-1000 Brussels 2017 CEN All rights of exploitation in any form and by any means reserved worldwide for CEN national Members. Ref. No. EN ISO 19017:2017 ENational forewordThis British Standard is the UK implementation of EN ISO 19017:2017. It is identica

8、l to ISO 19017:2015. It supersedes BS ISO 19017:2015, which is withdrawn.The UK participation in its preparation was entrusted to Technical Committee NCE/9, Nuclear fuel cycle technology.A list of organizations represented on this committee can be obtained on request to its secretary.This publicatio

9、n does not purport to include all the necessary provisions of a contract. Users are responsible for its correct application. The British Standards Institution 2018 Published by BSI Standards Limited 2018ISBN 978 0 580 96935 5ICS 17.240; 13.030.30; 27.120.30Compliance with a British Standard cannot c

10、onfer immunity from legal obligations.This British Standard was published under the authority of the Standards Policy and Strategy Committee on 31 January 2018.Amendments/corrigenda issued since publicationDate Text affected31 January 2018 This corrigendum renumbers BS ISO 19017:2015 as BS EN ISO 19

11、017:2017BRITISH STANDARDBS EN ISO 19017:2017EUROPEAN STANDARD NORME EUROPENNE EUROPISCHE NORM EN ISO 19017 October 2017 ICS 17.240; 27.120.30 English Version Guidance for gamma spectrometry measurement of radioactive waste (ISO 19017:2015) Lignes directrices pour le mesurage de dchets radioactifs pa

12、r spectromtrie gamma (ISO 19017:2015) Leitfaden fr gammaspektrometrische Messungen von radioaktivem Abfall (ISO 19017:2015) This European Standard was approved by CEN on 13 September 2017. CEN members are bound to comply with the CEN/CENELEC Internal Regulations which stipulate the conditions for gi

13、ving this European Standard the status of a national standard without any alteration. Up-to-date lists and bibliographical references concerning such national standards may be obtained on application to the CEN-CENELEC Management Centre or to any CEN member. This European Standard exists in three of

14、ficial versions (English, French, German). A version in any other language made by translation under the responsibility of a CEN member into its own language and notified to the CEN-CENELEC Management Centre has the same status as the official versions. CEN members are the national standards bodies

15、of Austria, Belgium, Bulgaria, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, Former Yugoslav Republic of Macedonia, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Sloveni

16、a, Spain, Sweden, Switzerland, Turkey and United Kingdom. EUROPEAN COMMITTEE FOR STANDARDIZATION COMIT EUROPEN DE NORMALISATION EUROPISCHES KOMITEE FR NORMUNG CEN-CENELEC Management Centre: Avenue Marnix 17, B-1000 Brussels 2017 CEN All rights of exploitation in any form and by any means reserved wo

17、rldwide for CEN national Members. Ref. No. EN ISO 19017:2017 EBS EN ISO 19017:2017EN ISO 19017:2017 (E) 3 European foreword The text of ISO 19017:2015 has been prepared by Technical Committee ISO/TC 85 “Nuclear energy, nuclear technologies, and radiological protection” of the International Organizat

18、ion for Standardization (ISO) and has been taken over as EN ISO 19017:2017 by Technical Committee CEN/TC 430 “Nuclear energy, nuclear technologies, and radiological protection” the secretariat of which is held by AFNOR. This European Standard shall be given the status of a national standard, either

19、by publication of an identical text or by endorsement, at the latest by April 2018, and conflicting national standards shall be withdrawn at the latest by April 2018. Attention is drawn to the possibility that some of the elements of this document may be the subject of patent rights. CEN shall not b

20、e held responsible for identifying any or all such patent rights. According to the CEN-CENELEC Internal Regulations, the national standards organizations of the following countries are bound to implement this European Standard: Austria, Belgium, Bulgaria, Croatia, Cyprus, Czech Republic, Denmark, Es

21、tonia, Finland, Former Yugoslav Republic of Macedonia, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and the United Kingdom. Endorsement n

22、otice The text of ISO 19017:2015 has been approved by CEN as EN ISO 19017:2017 without any modification. BS EN ISO 19017:2017ISO 19017:2015(E)Foreword ivIntroduction v1 Scope . 12 Terms and definitions . 13 Application . 73.1 General . 73.2 Typical applications 74 Measurement equipment 84.1 General

23、. 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 .144.4.5 Additional equipment .145 Calibration .14

24、5.1 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 Calculation of net peak count rates 196.3 Calculation

25、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 and procedures . 247.4 Quality control 247.5

26、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 EN ISO 19017:2017ISO 19017:2015(E)ForewordISO (the International Organization for Standardization)

27、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 been established has the right to be repres

28、ented 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 standardization.The procedures used to develo

29、p 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 accordance with the editorial rules of the ISO/I

30、EC 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 of any patent rights identified during th

31、e 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 endorsement.For an explanation on the meaning

32、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 responsible for this document is ISO/TC 85, Nucl

33、ear 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 collimators, the possible use of numerical

34、 simulation for calibration and uncertainty assessment, and gamma radiation detectors other than high-purity germanium semiconductors.iv ISO 2015 All rights reservedBS EN ISO 19017:2017ISO 19017:2015(E)IntroductionA variety of non-destructive assay techniques are routinely used within the nuclear in

35、dustry 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 containing radioactive waste.The methods and tec

36、hniques 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 in use for many years, through to stat

37、e 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 on experience of operating quantitative

38、 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 measurements made on packages containing

39、 radioactive waste. ISO 2015 All rights reserved vBS EN ISO 19017:2017Guidance for gamma spectrometry measurement of radioactive waste1 ScopeThis International Standard is applicable to gamma radiation measurements on radioactive waste.Radioactive waste can be found in different forms and exhibit a

40、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 (bitumen, cement, hydraulic binder, etc.); very low

41、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. The diversity of applications and system realizations

42、(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 impossible to provide specific guidance for all instances; th

43、e 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 influencing factors, contributing variables and performance req

44、uirements 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 adequately defined through the use of a structured requirem

45、ents 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 to gamma measurements of items other than radioactiv

46、e 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, the following terms and definitions apply.NOTE Definit

47、ions 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 determine quantitatively the amount of one or more radionuc

48、lides of interest contained in a packageINTERNATIONAL STANDARD ISO 19017:2015(E) ISO 2015 All rights reserved 1BS EN ISO 19017:2017ISO 19017:2015(E)2.2attenuationphysical process based on interaction between a radiation source and matter placed in the path of the radiation that results in a decrease

49、 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 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 correction the m