BS ISO 12749-3-2015 Nuclear energy nuclear technologies and radiological protection Vocabulary Nuclear fuel cycle《核能 核技术以及放射防护 词汇 核燃料循环》.pdf

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1、BSI Standards PublicationBS ISO 12749-3:2015Nuclear energy, nucleartechnologies, and radiologicalprotection VocabularyPart 3: Nuclear fuel cycleBS ISO 12749-3:2015 BRITISH STANDARDNational forewordThis British Standard is the UK implementation of ISO 12749-3:2015. The UK participation in its prepara

2、tion was entrusted to TechnicalCommittee NCE/2, Radiation protection and measurement. A list of organizations represented on this committee can be obtained on request to its secretary.This publication does not purport to include all the necessary provisions of a contract. Users are responsible for i

3、ts correct application. The British Standards Institution 2015.Published by BSI Standards Limited 2015ISBN 978 0 580 82908 6 ICS 01.040.13; 13.280 Compliance with a British Standard cannot confer immunity from legal obligations.This British Standard was published under the authority of the Standards

4、 Policy and Strategy Committee on 30 September 2015.Amendments/corrigenda issued since publicationDate T e x t a f f e c t e dBS ISO 12749-3:2015 ISO 2015Nuclear energy, nuclear technologies, and radiological protection Vocabulary Part 3: Nuclear fuel cyclenergie nuclaire, technologies nuclaires et

5、protection radiologique Vocabulaire Partie 3: Cycle de combustibles nuclairesINTERNATIONAL STANDARDISO12749-3First edition2015-08-15Reference numberISO 12749-3:2015(E)BS ISO 12749-3:2015ISO 12749-3:2015(E)ii ISO 2015 All rights reservedCOPYRIGHT PROTECTED DOCUMENT ISO 2015, Published in SwitzerlandA

6、ll rights reserved. Unless otherwise specified, no part 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

7、from either ISO at the address below or ISOs member body in the country of the requester.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 12749-3:2015ISO 12749-3:2015(E)Foreword ivIntroduction

8、 v1 Scope . 12 Structure of the vocabulary . 13 Terms and definitions . 23.1 General terms related to nuclear fuel cycle 23.2 Terms related to conversion and enrichment 63.3 Terms related to fuel fabrication . 73.4 Terms related to fuel characteristics 83.5 Terms related to transport of radioactive

9、material 103.6 Terms related to reprocessing 123.7 Terms related to radioactive waste 123.8 Terms related to decommissioning 173.9 Terms related to nuclear criticality safety 19Annex A (informative) Methodology used in the development of the vocabulary .21Annex B (informative) Alphabetical index 33B

10、ibliography .36 ISO 2015 All rights reserved iiiContents PageBS ISO 12749-3:2015ISO 12749-3:2015(E)ForewordISO (the International Organization for Standardization) is a worldwide federation of national standards bodies (ISO member bodies). The work of preparing International Standards is normally ca

11、rried 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, governmental and non-governmental, in liaison with ISO, also take part in the work

12、. 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 maintenance are described in the ISO/IEC Directives, Part 1. In particular the differ

13、ent 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 (see www.iso.org/directives).Attention is drawn to the possibility that some of the elements of this document may

14、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 the ISO list of patent declarations received (see www.iso.org/patents

15、).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 of ISO specific terms and expressions related to conformity assessment, as well as information about ISOs adherence to the WTO principles

16、in the Technical Barriers to Trade (TBT) see the following URL: Foreword - Supplementary Information The committee responsible for this document is ISO/TC 85, Nuclear energy, nuclear technologies, and radiological protection.This first edition cancels and replaces ISO 921:1997, of which it forms the

17、 subject of a technical revision.ISO 12749 consists of the following parts, under the general title Nuclear energy, nuclear technologies, and radiological protection: Part 2: Radiological protection Part 3: Nuclear fuel cycle Part 4: Dosimetry for radiation processingThe following parts are under pr

18、eparation: Part 5: Reactorsiv ISO 2015 All rights reservedBS ISO 12749-3:2015ISO 12749-3:2015(E)IntroductionThis part of ISO 12749 will provide terms and definitions for nuclear fuel cycle concepts dealing with specific subjects such as fuel fabrication, fuel characteristics, and nuclear criticality

19、 safety and with transport and radioactive waste related topics, excluding reactors operations. Terminological data are taken from ISO standards developed by TC 85/SC 5 and other technically validated documents issued by international organizations.Unambiguous communication of nuclear energy concept

20、s 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 any subject regarding nuclear energy activities. Nuclear fuels for different power reactors are produced according to differe

21、nt designs. However, several concepts are present in all of them and need to be designated by common terms and described by harmonized definitions in order to avoid misunderstandings. In another nuclear fuel technology subfield, difficulties arise due to the wide variety of units employed to measure

22、 the fuel burnout level. Thus, to enhance comprehension, it is advisable to adopt unified measure units.Conceptual arrangement of terms and definitions is based on concepts systems that show corresponding relationships among nuclear energy concepts. Such arrangement provides users with a structured

23、view of the nuclear energy sector and will facilitate common understanding of all related 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. ISO 2015 All rights r

24、eserved vBS ISO 12749-3:2015BS ISO 12749-3:2015Nuclear energy, nuclear technologies, and radiological protection Vocabulary Part 3: Nuclear fuel cycle1 ScopeThis part of ISO 12749 lists unambiguous terms and definitions related to nuclear fuel cycle concepts in the subject field of nuclear energy, e

25、xcluding reactor operations. It is intended to facilitate communication and promote common understanding.2 Structure of the vocabularyThe terminology entries are presented in the conceptual order of the English preferred terms. The structure of each entry is in accordance with ISO 10241-1:2011. All

26、the terms included in this part of ISO 12749 deal exclusively with nuclear fuel cycle. 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 definitions are essential to the correct understanding of the corr

27、esponding 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 information is also included, for example, the units in which

28、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 nuclear fuel cycle sub-subject field are taken into account. See Annex A for th

29、e methodology used to develop the vocabulary.nuclear fuel cycle3.1 General terms related to nuclear fuel cycle3.3Terms related to fuel fabrication3.4Terms related to fuel characteristics3.5Terms related to transport of radioactive material3.7Terms related to radio-active waste3.6Terms related torepr

30、ocessing3.2Terms related to conversion and enrichment3.8Terms related to decommi-ssioning3.9 Terms related to nuclear criticality safetyINTERNATIONAL STANDARD ISO 12749-3:2015(E) ISO 2015 All rights reserved 1BS ISO 12749-3:2015ISO 12749-3:2015(E)3 Terms and definitions3.1 General terms related to n

31、uclear fuel cycle3.1.1nuclear fuelfissionable nuclear material used in a reactor core or intended for use in a reactor core3.1.1.1nuclear fuel cycleoperations associated with the production of nuclear energyNote 1 to entry: The nuclear fuel cycle includes the following stages:a) mining and processin

32、g of uranium or thorium ores;b) conversion;c) enrichment of uranium;d) manufacture of nuclear fuel (3.1.1);e) uses of the nuclear fuel;f) reprocessing (3.1.1.1.2.2) and recycling (3.1.1.1.2.3) of spent fuel;g) temporary radioactive material storage (3.1.1.1.2.1)of spent fuel and radioactive waste (3

33、.7.1) from fuel fabrication (3.1.1.1.1.3) and reprocessing (3.1.1.1.2.2) and disposal of spent nuclear fuel (3.1.1.1.5) open fuel cycle (3.1.1.7) or high-level waste (closed fuel cycle (3.1.1.8);h) any related research and development activities;i) transport of radioactive material;j) all waste mana

34、gement (3.7.7) activities including decommissioning (3.8.1) relating to operations associated with the production of nuclear energy.Note 2 to entry: Reactor operation and other activities at a reactor site are not addressed in this part of ISO 12749, but are to be addressed in ISO 12749-5.SOURCE: Ad

35、apted from IAEA Safety Glossary, 2007 Edition, modified By splitting the definition into a definition and a note.3.1.1.1.1front endsteps of the nuclear fuel cycle (3.1.1.1) ending with fuel introduction into the reactor core3.1.1.1.1.1nuclear material conversionmodification of the chemical compositi

36、on of nuclear material so as to facilitate its further use or processing; in particular, to provide feed material for enrichment of isotopes of interest and/or reactor fuel fabrication (3.1.1.1.1.3)Note 1 to entry: To produce material for fuel fabrication (3.1.1.1.1.3), the following are examples of

37、 conversion that can be carried out: U3O8or UF6to uranium dioxide (UO2), U or Pu nitrate to oxide, or U or Pu oxides to metal.SOURCE: IAEA Safeguards Glossary, 2001 Edition, modified By splitting the definition into a definition and note 1 to entry.2 ISO 2015 All rights reservedBS ISO 12749-3:2015IS

38、O 12749-3:2015(E)3.1.1.1.1.2isotope enrichmentisotope separation process by which the fractional abundance of a specified isotope in an element is increased such as increasing the abundance of 235U relative to natural uranium (3.1.1.2) or increasing the abundance of the D2O in waterNote 1 to entry:

39、Usually, the term will be “enrichment”.3.1.1.1.1.2.1enriched fuelfuel made with uranium that has been modified by increasing the abundance of the fissile isotope 235U3.1.1.1.1.3fuel fabricationprocess for manufacturing fuel elements (3.3.6) or other reactor components containing nuclear materialNote

40、 1 to entry: Manufacturing process includes nuclear material conversion (3.1.1.1.1.1), storage, and physic-chemical analyses of materials.SOURCE: IAEA Safeguards Glossary, 2001 Edition3.1.1.1.2back endsteps of the nuclear fuel cycle (3.1.1.1) beginning with the final removal of the fuel from the rea

41、ctor coreNote 1 to entry: The processes can include radioactive material storage (3.1.1.1.2.1)at or away from reactor, reprocessing (3.1.1.1.2.2), recycling (3.1.1.1.2.3), conditioning and disposal.SOURCE: IAEA-TECDOC-1613 “Nuclear fuel cycle information system”, 2009, modified By splitting the defi

42、nition into a definition and note 1 to entry.3.1.1.1.2.1radioactive material storageholding of radioactive sources, spent nuclear fuel (3.1.1.1.5), or radioactive waste (3.7.1) in a facility that provides for containment with the intention of retrievalSOURCE: IAEA Safety Glossary 20073.1.1.1.2.2repr

43、ocessingprocess or operation of extracting fission products (3.1.5) from spent nuclear fuel (3.1.1.1.5) to enable reuse of the nuclear fuel (3.1.1)in a reactor3.1.1.1.2.3recyclinguse, for the fabrication of nuclear fuel (3.1.1), of fissionable materials (3.1.3) separated from spent nuclear fuel (3.1

44、.1.1.5)3.1.1.1.2.3.1mixed oxide fuelMOX fuelmixture of oxides of different fissionable elementsNote 1 to entry: In the nuclear fuel cycle (3.1.1.1), MOX is interpreted as mixed uranium and plutonium oxides unless otherwise specified.3.1.1.1.2.4encapsulationencasement of radioactive contaminants in a

45、 suitable material for final disposal ISO 2015 All rights reserved 3BS ISO 12749-3:2015ISO 12749-3:2015(E)3.1.1.1.3burnupaverage energy released by a defined region of the fuel during its irradiationNote 1 to entry: This region could be a complete fuel assembly (3.3.6.1) or some part of the assembly

46、. Burnup is commonly expressed as energy released per mass of initial fissionable actinides (3.1.8) (uranium only for this part of ISO 12749). Units commonly used are expressed in megawatt day per metric ton of initial uranium (MWd/t) or gigawatt day per metric ton of initial uranium (GWd/t).SOURCE:

47、 ISO 27468:2011, 3.43.1.1.1.4used nuclear fuelfuel that has been activated in the fission process of a nuclear reactor core3.1.1.1.5spent nuclear fuelfuel that has been burned in the core of a nuclear reactor and is no longer efficient to maintain its specific nuclear service3.1.1.2natural uraniumel

48、emental uranium containing the naturally occurring uranium isotopes (approximately 99,28% 238U, 0,72% 235U by mass, and small amount of 234U)SOURCE: Adapted from IAEA Safety Glossary, 20073.1.1.2.1depleted uraniumuranium containing 235U fractional abundance less than that of natural uranium (3.1.1.2

49、)Note 1 to entry: Depleted uranium is the complement product to enriched uranium (3.1.1.2.2) where in the former, 238U mass fraction is higher than that of natural uranium (3.1.1.2).SOURCE: Adapted from IAEA Safety Glossary, 20073.1.1.2.2enriched uraniumuranium containing a greater mass fraction or percentage of 235U than in natural uranium (3.1.1.2)SOURCE: IAEA Safety Glossary, 2007 Edition, modified By adding “fraction or” before “percentage” and replacing “0,72%” with “in natural uranium”.