1、BSI Standards PublicationBS EN 16603-10-12:2014Space engineering Methodfor the calculation of radiationreceived and its effects, and apolicy for design marginsBS EN 16603-10-12:2014 BRITISH STANDARDNational forewordThis British Standard is the UK implementation of EN 16603-10-12:2014.The UK particip
2、ation in its preparation was entrusted to Technical Com-mittee ACE/68, Space systems and operations.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 provi-sions of a contract. Users are re
3、sponsible for its correct application. The British Standards Institution 2014.Published by BSI Standards Limited 2014ISBN 978 0 580 83978 8ICS 49.140Compliance with a British Standard cannot confer immunity from legal obligations.This British Standard was published under the authority of the Stand-a
4、rds Policy and Strategy Committee on 31 July 2014.Amendments/corrigenda issued since publicationDate T e x t a f f e c t e dBS EN 16603-10-12:2014EUROPEAN STANDARD NORME EUROPENNE EUROPISCHE NORM EN 16603-10-12 July 2014 ICS 49.140 English version Space engineering - Method for the calculation of ra
5、diation received and its effects, and a policy for design margins Ingnirie spatiale - Procd pour le calcul de rayonnement reue et ses effets, et une politique de marges de conception Raumfahrttechnik - Methoden zur Berechnung von Strahlungsdosis, -wirkung und Leitfaden fr Toleranzen im Entwurf This
6、European Standard was approved by CEN on 9 February 2014. CEN and CENELEC 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 bibliographi
7、cal references concerning such national standards may be obtained on application to the CEN-CENELEC Management Centre or to any CEN and CENELEC member. This European Standard exists in three official versions (English, French, German). A version in any other language made by translation under the re
8、sponsibility of a CEN and CENELEC member into its own language and notified to the CEN-CENELEC Management Centre has the same status as the official versions. CEN and CENELEC members are the national standards bodies and national electrotechnical committees of Austria, Belgium, Bulgaria, Croatia, Cy
9、prus, 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, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and United K
10、ingdom. CEN-CENELEC Management Centre: Avenue Marnix 17, B-1000 Brussels 2014 CEN/CENELEC All rights of exploitation in any form and by any means reserved worldwide for CEN national Members and for CENELEC Members. Ref. No. EN 16603-10-12:2014 EBS EN 16603-10-12:2014EN 16603-10-12:2014 (E) 2 Table o
11、f contents Foreword 6 1 Scope . 7 2 Normative references . 8 3 Terms, definitions and abbreviated terms 9 3.1 Terms from other standards 9 3.2 Terms specific to the present standard . 9 3.3 Abbreviated terms. 20 4 Principles 26 4.1 Radiation effects . 26 4.2 Radiation effects evaluation activities .
12、 27 4.3 Relationship with other standards . 32 5 Radiation design margin 33 5.1 Overview 33 5.1.1 Radiation environment specification 33 5.1.2 Radiation margin in a general case . 33 5.1.3 Radiation margin in the case of single events . 34 5.2 Margin approach . 34 5.3 Space radiation environment 36
13、5.4 Deposited dose calculations . 37 5.5 Radiation effect behaviour 37 5.5.1 Uncertainties associated with EEE component radiation susceptibility data . 37 5.5.2 Component dose effects . 38 5.5.3 Single event effects . 39 5.5.4 Radiation-induced sensor background 40 5.5.5 Biological effects . 40 5.6
14、 Establishment of margins at project phases 41 5.6.1 Mission margin requirement 41 5.6.2 Up to and including PDR . 41 BS EN 16603-10-12:2014EN 16603-10-12:2014 (E) 3 5.6.3 Between PDR and CDR 42 5.6.4 Hardness assurance post-CDR . 42 5.6.5 Test methods 43 6 Radiation shielding 44 6.1 Overview 44 6.2
15、 Shielding calculation approach . 44 6.2.1 General . 44 6.2.2 Simplified approaches . 48 6.2.3 Detailed sector shielding calculations 50 6.2.4 Detailed 1-D, 2-D or full 3-D radiation transport calculations . 51 6.3 Geometry considerations for radiation shielding model . 52 6.3.1 General . 52 6.3.2 G
16、eometry elements . 53 6.4 Uncertainties . 55 7 Total ionising dose . 56 7.1 Overview 56 7.2 General . 56 7.3 Relevant environments . 56 7.4 Technologies sensitive to total ionising dose 57 7.5 Radiation damage assessment . 59 7.5.1 Calculation of radiation damage parameters . 59 7.5.2 Calculation of
17、 the ionizing dose . 59 7.6 Experimental data used to predict component degradation . 60 7.7 Experimental data used to predict material degradation . 61 7.8 Uncertainties . 61 8 Displacement damage 62 8.1 Overview 62 8.2 Displacement damage expression 62 8.3 Relevant environments . 63 8.4 Technologi
18、es susceptible to displacement damage 63 8.5 Radiation damage assessment . 64 8.5.1 Calculation of radiation damage parameters . 64 8.5.2 Calculation of the DD dose 64 8.6 Prediction of component degradation 68 8.7 Uncertainties . 68 9 Single event effects 69 BS EN 16603-10-12:2014EN 16603-10-12:201
19、4 (E) 4 9.1 Overview 69 9.2 Relevant environments . 70 9.3 Technologies susceptible to single event effects 70 9.4 Radiation damage assessment . 71 9.4.1 Prediction of radiation damage parameters . 71 9.4.2 Experimental data and prediction of component degradation 76 9.5 Hardness assurance . 78 9.5.
20、1 Calculation procedure flowchart 78 9.5.2 Predictions of SEE rates for ions . 78 9.5.3 Prediction of SEE rates of protons and neutrons . 80 10 Radiation-induced sensor backgrounds 83 10.1 Overview 83 10.2 Relevant environments . 83 10.3 Instrument technologies susceptible to radiation-induced backg
21、rounds 87 10.4 Radiation background assessment . 87 10.4.1 General . 87 10.4.2 Prediction of effects from direct ionisation by charged particles 88 10.4.3 Prediction of effects from ionisation by nuclear interactions 88 10.4.4 Prediction of effects from induced radioactive decay . 89 10.4.5 Predicti
22、on of fluorescent X-ray interactions . 89 10.4.6 Prediction of effects from induced scintillation or Cerenkov radiation in PMTs and MCPs . 90 10.4.7 Prediction of radiation-induced noise in gravity-wave detectors. 90 10.4.8 Use of experimental data from irradiations 91 10.4.9 Radiation background ca
23、lculations 91 11 Effects in biological material . 94 11.1 Overview 94 11.2 Parameters used to measure radiation . 94 11.2.1 Basic physical parameters 94 11.2.2 Protection quantities 95 11.2.3 Operational quantities . 97 11.3 Relevant environments . 97 11.4 Establishment of radiation protection limit
24、s . 98 11.5 Radiobiological risk assessment . 99 11.6 Uncertainties . 100 References . 102 BS EN 16603-10-12:2014EN 16603-10-12:2014 (E) 5 Bibliography . 104 Figures Figure 9-1: Procedure flowchart for hardness assurance for single event effects. 79 Tables Table 4-1: Stages of a project and radiatio
25、n effects analyses performed 28 Table 4-2: Summary of radiation effects parameters, units and examples 29 Table 4-3: Summary of radiation effects and cross-references to other chapters 30 Table 6-1: Summary table of relevant primary and secondary radiations to be quantified by shielding model as a f
26、unction of radiation effect and mission type . 46 Table 6-2: Description of different dose-depth methods and their applications . 48 Table 7-1: Technologies susceptible to total ionising dose effects 58 Table 8-1: Summary of displacement damage effects observed in components as a function of compone
27、nt technology 66 Table 8-2: Definition of displacement damage effects 67 Table 9-1: Possible single event effects as a function of component technology and family. 71 Table 10-1: Summary of possible radiation-induced background effects as a function of instrument technology 84 Table 11-1: Radiation
28、weighting factors 96 Table 11-2: Tissue weighting factors for various organs and tissue (male and female). 96 Table 11-3: Sources of uncertainties for risk estimation from atomic bomb data. 101 Table 11-4: Uncertainties of risk estimation from the space radiation field 101 BS EN 16603-10-12:2014EN 1
29、6603-10-12:2014 (E) 6 Foreword This document (EN 16603-10-12:2014) has been prepared by Technical Committee CEN/CLC/TC 5 “Space”, the secretariat of which is held by DIN. This standard (EN 16603-10-12:2014) originates from ECSS-E-ST-10-12C. This European Standard shall be given the status of a natio
30、nal standard, either by publication of an identical text or by endorsement, at the latest by January 2015, and conflicting national standards shall be withdrawn at the latest by January 2015. Attention is drawn to the possibility that some of the elements of this document may be the subject of paten
31、t rights. CEN and/or CENELEC shall not be held responsible for identifying any or all such patent rights. This document has been developed to cover specifically space systems and has therefore precedence over any EN covering the same scope but with a wider domain of applicability (e.g. : aerospace).
32、 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, Estonia, Finland, Former Yugoslav Republic of Macedonia, France, Ge
33、rmany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Romania, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and the United Kingdom.” BS EN 16603-10-12:2014EN 16603-10-12:2014 (E) 7 1 Scope This standard is a part of th
34、e System Engineering branch of the ECSS engineering standards and covers the methods for the calculation of radiation received and its effects, and a policy for design margins. Both natural and man-made sources of radiation (e.g. radioisotope thermoelectric generators, or RTGs) are considered in the
35、 standard. This standard applies to the evaluation of radiation effects on all space systems. This standard applies to all product types which exist or operate in space, as well as to crews of manned space missions. The standard aims to implement a space system engineering process that ensures commo
36、n understanding by participants in the development and operation process (including Agencies, customers, suppliers, and developers) and use of common methods in evaluation of radiation effects. This standard is complemented by ECSS-E-HB-10-12 “Radiation received and its effects and margin policy han
37、dbook”. This standard may be tailored for the specific characteristic and constrains of a space project in conformance with ECSS-S-ST-00. BS EN 16603-10-12:2014EN 16603-10-12:2014 (E) 8 2 Normative references The following normative documents contain provisions which, through reference in this text,
38、 constitute provisions of this ECSS Standard. For dated references, subsequent amendments to, or revision of any of these publications do not apply, However, parties to agreements based on this ECSS Standard are encouraged to investigate the possibility of applying the more recent editions of the no
39、rmative documents indicated below. For undated references, the latest edition of the publication referred to applies. EN reference Reference in text Title EN 16601-00-01 ECSS-S-ST-00-01 ECSS system Glossary of terms EN 16603-10-04 ECSS-E-ST-10-04 Space engineering Space environment EN 16603-10-09 EC
40、SS-E-ST-10-09 Space engineering Reference coordinate system EN 16602-30 ECSS-Q-ST-30 Space product assurance Dependability EN 16602-60 ECSS-Q-ST-60 Space product assurance Electrical, electronic and electromechanical (EEE) components BS EN 16603-10-12:2014EN 16603-10-12:2014 (E) 9 3 Terms, definitio
41、ns and abbreviated terms 3.1 Terms from other standards For the purpose of this Standard, the terms and definitions from ECSS-ST-00-01 apply, in particular for the following terms: derating subsystem 3.2 Terms specific to the present standard 3.2.1 absorbed dose energy absorbed locally per unit mass
42、 as a result of radiation exposure which is transferred through ionisation, displacement damage and excitation and is the sum of the ionising dose and non-ionising dose NOTE 1 It is normally represented by D, and in accordance with the definition, it can be calculated as the quotient of the energy i
43、mparted due to radiation in the matter in a volume element and the mass of the matter in that volume element. It is measured in units of gray, Gy (1 Gy = 1 J kg-1(= 100 rad). NOTE 2 The absorbed dose is the basic physical quantity that measures radiation exposure. 3.2.2 air kerma energy of charged p
44、articles released by photons per unit mass of dry air NOTE It is normally represented by K. 3.2.3 ambient dose equivalent, H*(d) dose at a point equivalent to the one produced by the corresponding expanded and aligned radiation field in the ICRU sphere at a specific depth on the radius opposing the
45、direction of the aligned field NOTE 1 It is normally represented by H*(d), where d is the specific depth used in its definition, in mm. NOTE 2 H*(d) is relevant to strongly penetrating radiation. The value normally used is 10 mm, BS EN 16603-10-12:2014EN 16603-10-12:2014 (E) 10 but dose equivalent a
46、t other depths can be used when the dose equivalent at 10 mm provides an unacceptable underestimate of the effective dose. 3.2.4 bremsstrahlung high energy electromagnetic radiation in the X-ray energy range emitted by charged particles slowing down by scattering off atomic nuclei NOTE The primary p
47、article is ultimately absorbed while the bremsstrahlung can be highly penetrating. In space the most common source of bremsstrahlung is electron scattering. 3.2.5 component device that performs a function and consists of one or more elements joined together and which cannot be disassembled without d
48、estruction 3.2.6 continuous slowing down approximation range (CSDA) integral pathlength travelled by charged particles in a material assuming no stochastic variations between different particles of the same energy, and no angular deflections of the particles 3.2.7 COTS commercial electronic componen
49、t readily available off-the-shelf, and not manufactured, inspected or tested in accordance with military or space standards 3.2.8 critical charge minimum amount of charge collected at a sensitive node due to a charged particle strike that results in a SEE 3.2.9 cross-section probability of a single event effect occurring per unit incident particle fluence NOTE This is experimentally measured as the number of events recorded per unit fluence. 3.2.10 cross-section probability of a particle interaction per unit incident particle fluence NOTE It is sometimes referred to a
