BS ISO 12749-2-2013 Nuclear energy nuclear technologies and radiological protection Vocabulary Radiological protection《核能、核技术以及放射防护 词汇 放射防护 n》.pdf

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1、BSI Standards PublicationBS ISO 12749-2:2013Nuclear energy, nucleartechnologies, and radiologicalprotection VocabularyPart 2: Radiological protectionBS ISO 12749-2:2013 BRITISH STANDARDNational forewordThis British Standard is the UK implementation of ISO 12749-2:2013.The UK participation in its pre

2、paration was entrusted to TechnicalCommittee NCE/2, Radiation protection and measurement.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

3、its correctapplication. The British Standards Institution 2013. Published by BSI StandardsLimited 2013ISBN 978 0 580 75626 9ICS 01.040.13; 13.280Compliance with a British Standard cannot confer immunity fromlegal obligations.This British Standard was published under the authority of theStandards Pol

4、icy and Strategy Committee on 30 September 2013.Amendments issued since publicationDate Text affectedBS ISO 12749-2:2013 ISO 2013Nuclear energy, nuclear technologies, and radiological protection Vocabulary Part 2: Radiological protectionnergie nuclaire, technologies nuclaires et protection radiologi

5、que Vocabulaire Partie 2: Protection radiologiqueINTERNATIONAL STANDARDISO12749-2First edition2013-09-15Reference numberISO 12749-2:2013(E)BS ISO 12749-2:2013ISO 12749-2:2013(E)ii ISO 2013 All rights reservedCOPYRIGHT PROTECTED DOCUMENT ISO 2013All rights reserved. Unless otherwise specified, no par

6、t of this publication may be reproduced 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 bo

7、dy in the country of the requester.ISO copyright officeCase postale 56 CH-1211 Geneva 20Tel. + 41 22 749 01 11Fax + 41 22 749 09 47E-mail copyrightiso.orgWeb www.iso.orgPublished in SwitzerlandBS ISO 12749-2:2013ISO 12749-2:2013(E) ISO 2013 All rights reserved iiiContents PageForeword iv0. Introduct

8、ion .vScope 11 General terms related to radiological protection. 12 Terms related to biological effect . 43 Terms related to radiological exposure 54 Terms related to radiological monitoring 95 Terms related to measurement 126 Terms related to technical aspects .147 Terms related to regulation .16An

9、nex A (informative) Methodology used in the development of the vocabulary .20Annex B (informative) Alphabetical index 30Bibliography .33BS ISO 12749-2:2013ISO 12749-2:2013(E)ForewordISO (the International Organization for Standardization) is a worldwide federation of national standards bodies (ISO m

10、ember 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 represented on that committee. International organizations, governm

11、ental 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 develop this document and those intended for its further maintenanc

12、e 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/IEC Directives, Part 2. www.iso.org/directivesAttention is dra

13、wn 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 the development of the document will be in the Introduction and/or on

14、the ISO list of patent declarations received. www.iso.org/patentsAny trade name used in this document is information given for the convenience of users and does not constitute an endorsement. The committee responsible for this document is ISO/TC 85, Nuclear energy, nuclear technologies, and radiolog

15、ical protection.ISO 12749 consists of the following parts, under the general title Nuclear energy, nuclear technologies, and radiological protection Vocabulary. Part 2: Radiological protectionThe following parts are under preparation: Part 3: Nuclear fuel cycleiv ISO 2013 All rights reservedBS ISO 1

16、2749-2:2013ISO 12749-2:2013(E)0. Introduction0.1 GeneralThis part of ISO 12749 provides terms and definitions for general nuclear energy concepts dealing with radiological protection and other related concepts, such as means of protection for human health and environment, measurement methods and ins

17、truments, and the prevision or direct determination of the effect of ionizing radiations on the body. Terminological data are taken from International Standards developed by the SC 2 and other technically validated documents such as the IAEA Glossary, IAEA BSS, ICRP, ICRU 60, ICRU 51, VIM, and BIPM.

18、Unambiguous communication of radiological protection concepts is crucial, taking into account the relevant implications that may arise from misunderstandings with regard to equipment and materials involved in the standards dealing with this subject. The market of radiological protection is a heterog

19、eneous one because it comprises equipment designed, built, and operated along the safe practices defined by radiological protection specialists. This market also includes nuclear reactors, nuclear fuel cycle, and instruments to monitor both personnel and facilities and sites. In view of the foregoin

20、g, a large number of people having different levels of scientific and technical knowledge are involved; thus, there can be widely divergent understandings and assumptions about concepts. The results are poor communication, high risk of accidents, and duplication of effort as different groups are goi

21、ng to define concepts according to their perspectives.Conceptual arrangement of terms and definitions is based on concepts systems that show corresponding relationships among radiological protection concepts. Such arrangement provides users with a structured view of this special subdomain within the

22、 nuclear energy sector and will facilitate common understanding of radiological protection concepts. Besides, concepts systems and conceptual arrangement of terminological data will be helpful to any kind of user because it will promote clear, accurate, and useful communication. At the end of this p

23、art of ISO 12749, an alphabetical index shows the terms followed by their corresponding notation.0.2 Structure of the vocabularyThe terminology entries are presented in the conceptual order of the English preferred terms. Both a systematic index and an alphabetical index are included. The structure

24、of each entry is in accordance with ISO 10241-1:2011.All the terms included in this part of ISO 12749 deal exclusively with radiation protection. When selecting terms and definitions, special care has been taken to include the terms that need to be defined, that is to say, either because the definit

25、ions are essential to the correct understanding of the corresponding concepts or because some specific ambiguities need to be addressed.The notes appended to certain definitions offer clarification or examples to facilitate understanding of the concepts described. In certain cases, miscellaneous inf

26、ormation is also included, for example, the units in which a quantity is normally measured, recommended parameter values, references, etc.According to the title, the vocabulary deals with concepts belonging to the general nuclear energy subject field within which concepts in the radiological protect

27、ion sub-subject field are taken into account. ISO 2013 All rights reserved vBS ISO 12749-2:2013BS ISO 12749-2:2013Nuclear energy, nuclear technologies, and radiological protection Vocabulary Part 2: Radiological protectionScopeThis part of ISO 12749 lists unambiguous terms and definitions related to

28、 radiological protection concepts in the subject field of nuclear energy. It is intended to facilitate communication and promote common understanding.1 General terms related to radiological protection1.1radiological protectionradiation protectionprotection of people and the environment from the harm

29、ful effects of exposure to ionizing radiation and the means for achieving such protectionSOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection 2007 Edition, modified By adding “and the environment”.1.1.1radiation sourceanything (apparatus, substance, installation)

30、that may cause radiation exposure, such as by emitting ionization radiation or releasing radioactive substances or materialsSOURCE: ISO 14152:20011.1.1.1radioactivitystochastic process whereby nuclei undergo spontaneous disintegration, usually accompanied by the emission of subatomic particles, or p

31、hotonsSOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection 2007 Edition, modified By deleting “random” between “spontaneous” and “disintegration”.1.1.1.1.1radioactive materialmaterial of which one or more constituents exhibit radioactivity (1.1.1.1)Note 1 to entry

32、: For special purposes such as regulation, this term may be restricted to radioactive material (1.1.1.1.1) with an activity or a specific activity greater than a specified value.SOURCE: ISO 921:19971.1.1.1.1.1radioactive contaminationradioactive substances on surfaces, or within solids, liquids, or

33、gases (including the human body), where their presence is unintended or undesirable, or the process giving rise to their presence in such placesSOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection 2007 EditionINTERNATIONAL STANDARD ISO 12749-2:2013(E) ISO 2013 All

34、 rights reserved 1BS ISO 12749-2:2013ISO 12749-2:2013(E)1.1.1.1.1.1.1surface contaminationradioactive material (1.1.1.1.1) deposited on surfaces of facilities (floor surface, work bench tops, machines, etc.), equipment, or personnel1.1.2equilibrium equivalent radon concentrationconcentration of rado

35、n in air, in equilibrium with its short-lived decay products, which would have the same potential alpha energy concentration as the existing non-equilibrium mixtureSOURCE: UNSCEAR 2006, Appendix E1.1.2.1equilibrium factorratio of the equilibrium equivalent concentration of radon to the actual radon

36、concentrationSOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection 2007 Edition1.1.3justificationprocess of determining for a planned exposure situation whether a practice is, overall, beneficial or for an emergency exposure situation or an existing exposure situat

37、ion whether a proposed protective action or remedial action is likely, overall, to be beneficialSOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards - Interim Edition IAEA Safety Standards Series GSR Part 3, 20111.1.4optimization of protectionprocess of

38、determining what level of protection and safety makes exposures, and the probability and magnitude of potential exposures, as low as reasonably achievable, economic and societal factors being taken into accountSOURCE: ICRP 103, modified By adding “as low as reasonably achievable, economic and societ

39、al factors being taken into account” at the end.1.1.5dosemeasure of the energy deposited by radiation in a targetSOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards - Interim Edition IAEA Safety Standards Series GSR Part 3, 2011Note 1 to entry: Abbrevia

40、tion for any of the existing dose quantities such as absorbed dose, effective dose, or equivalent dose.Note 2 to entry: If unqualified, the dose quantity should be indicated by the context.1.1.6dose limitlimit on equivalent dose (3.3.2) and/or on effective dose (3.3.4) that is applied for exposure t

41、o individuals in order to prevent the occurrence of radiation-induced deterministic effects or to limit the probability of radiation-related stochastic effects to an acceptable levelSOURCE: National Council on Radiation Protection and Measurements USA, Glossary, modified By changing “radiation dose”

42、 to “equivalent dose” and adding “and/or on effective dose”.2 ISO 2013 All rights reservedBS ISO 12749-2:2013ISO 12749-2:2013(E)1.1.6.1partial-body doseequivalent dose (3.3.2) to tissue, organs, or parts of the bodyNote 1 to entry: Identified by the name of the part of the particular tissue, organ,

43、or body, e.g. bone marrow dose, skin dose, hand dose, testes dose, or dose to the lens of the eyes.Note 2 to entry: The unit of equivalent dose (3.3.2) is joule per kilogram (Jkg1) and its special name is sievert (Sv).SOURCE: ISO 15382:2002, modified By stating the examples in Note 1 and adding Note

44、 2.1.1.6.2annual dosedose from external exposure (3.2) in a year plus the committed dose (3.1.2) from intakes of radionuclides in that yearSOURCE: IAEA Basic Safety Standards, March 20111.1.6.3total dosedose from external exposure (3.2) in a given period plus the committed dose (3.1.2) from intakes

45、of radionuclides in that same periodSOURCE: IAEA Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards - Interim Edition IAEA Safety Standards Series GSR Part 3, 20111.1.7dose constraintprospective and source-related value of individual dose or risk that is used

46、in planned exposure situations (3.4.1) as a parameter for the optimization of protection (1.1.4) and safety for the source, and that serves as a boundary in defining the range of options in optimizationSOURCE: IAEA Radiation Protection and Safety of Radiation Sources: International Basic Safety Stan

47、dards - Interim Edition IAEA Safety Standards Series GSR Part 3, 20111.1.8derived limitlimit on a measurable quantity set, on the basis of a model, such that compliance with the derived limit may be assumed to ensure compliance with a primary limitSOURCE: IAEA Safety Glossary Terminology Used in Nuc

48、lear Safety and Radiation Protection 2007 Edition1.1.9derived air concentrationDACderived limit (1.1.8) on the activity concentration in air of a specified radionuclide, calculated such that reference individual, breathing air with constant contamination at the concentration while performing light p

49、hysical activity for a working year, would receive an intake corresponding to the annual limit on intake (1.1.9.1) for the radionuclide in questionSOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection 2007 Edition, modified By replacing “Reference Man” with “reference individual”.Note 1 to entry: The parameter values recommended by the International Commission on Radiological Protection for calculating DACs are a breathing rate of 1,2 m3/h and a worki