SIST EN 16603-10-12:2014
(Main)Space engineering - Method for the calculation of radiation received and its effects, and a policy for design margins
Space engineering - Method for the calculation of radiation received and its effects, and a policy for design margins
EN 16603-10-12 is a part of the 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 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 common 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 handbook”. This standard may be tailored for the specific characteristic and constrains of a space project in conformance with ECSS-S-ST-00.
Raumfahrttechnik - Methoden zur Berechnung von Strahlungsdosis, -wirkung und Leitfaden für Toleranzen im Entwurf
Ingéniérie spatiale - Procédé pour le calcul de rayonnement reçue et ses effets, et une politique de marges de conception
La présente norme fait partie de la branche Ingénierie système des normes d'ingénierie ECSS et décrit les méthodes de calcul des rayonnements reçus et de leurs effets, ainsi que la politique relative aux marges de conception. Les sources de rayonnement naturelles ou d'origine humaine (par exemple les générateurs thermoélectriques radio-isotopiques ou RTG) sont prises en compte dans cette norme.
La présente norme s'applique à l'évaluation des effets des rayonnements sur tous les systèmes spatiaux.
Elle s'applique à tous les types de produits existant ou fonctionnant dans l'espace, ainsi qu'aux équipes des missions spatiales habitées. La présente norme a pour objet de mettre en œuvre un processus d'ingénierie des systèmes spatiaux permettant de garantir une compréhension commune par les participants au processus de développement et d'exploitation (y compris les agences, clients, fournisseurs et développeurs) et l'utilisation de méthodes communes d'évaluation des effets des rayonnements.
La présente norme est complétée par ECSS-E-HB-10-12 « Radiation received and its effects and margin policy handbook ».
La présente norme peut être adaptée aux caractéristiques et contraintes spécifiques d'un projet spatial conformément à l'ECSS-S-ST-00.
Vesoljska tehnika - Metoda za izračun prejetega sevanja in njegovih učinkov ter politika pri zasnovi mejnih vrednosti
Standard EN 16603-10-12 je del veje sistemskega načrtovanja standardov tehnike ECSS (evropsko sodelovanje za standardizacijo na področju vesolja) in obravnava metode za izračun prejetega sevanja in njegovih učinkov ter politiko pri zasnovi mejnih vrednosti. V tem standardu so obravnavani naravni in umetni viri sevanja (npr. radioizotopni termoelektrični generatorji ali RTG). Ta standard se uporablja za ocenjevanje učinkov sevanja na vse vesoljske sisteme. Ta standard se uporablja za vse vrste proizvodov, ki obstajajo ali delujejo v vesolju, ter tudi za ekipe vesoljskih misij z osebjem. Cilj standarda je izvajati proces tehnike vesoljskega sistema, ki zagotavlja splošno razumevanje udeležencev pri procesu razvoja in delovanja (vključno z agencijami, strankami, dobavitelji in razvijalci) ter uporabi skupnih metod za ocenjevanje učinkov sevanja. Ta standard dopolnjuje standard ECSS-E-HB-10-12, tj. priročnik o prejetem sevanju in njegovih učinkih ter politiki pri zasnovi mejnih vrednosti. Ta standard se lahko prilagodi posameznim lastnostim in omejitvam vesoljskega projekta v skladu s standardom ECSS-S-ST-00.
General Information
Standards Content (Sample)
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.Raumfahrttechnik - Methoden zur Berechnung von Strahlungsdosis, -wirkung und Leitfaden für Toleranzen im EntwurfIngéniérie spatiale - Procédé pour le calcul de rayonnement reçue et ses effets, et une politique de marges de conceptionSpace engineering - Method for the calculation of radiation received and its effects, and a policy for design margins49.140Vesoljski sistemi in operacijeSpace systems and operations17.240Merjenje sevanjaRadiation measurementsICS:Ta slovenski standard je istoveten z:EN 16603-10-12:2014SIST EN 16603-10-12:2014en01-oktober-2014SIST EN 16603-10-12:2014SLOVENSKI
STANDARD
SIST EN 16603-10-12:2014
EUROPEAN STANDARD NORME EUROPÉENNE EUROPÄISCHE NORM
EN 16603-10-12
July 2014 ICS 49.140
English version
Space engineering - Method for the calculation of radiation received and its effects, and a policy for design margins
Ingéniérie spatiale - Procédé pour le calcul de rayonnement reçue et ses effets, et une politique de marges de conception
Raumfahrttechnik - Methoden zur Berechnung von Strahlungsdosis, -wirkung und Leitfaden für Toleranzen im Entwurf This 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 bibliographical 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 responsibility 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, 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, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and United Kingdom.
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 E SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 2 Table of 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 . 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 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 Establishment of margins at project phases . 41 5.6.1 Mission margin requirement . 41 5.6.2 Up to and including PDR . 41 SIST EN 16603-10-12:2014
EN 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 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 Geometry 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 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 Technologies 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 SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (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 9.5.1 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 backgrounds . 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 Prediction 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 calculations . 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 limits . 98 11.5 Radiobiological risk assessment . 99 11.6 Uncertainties . 100 References . 102 SIST EN 16603-10-12:2014
EN 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 radiation 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 function 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 component 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 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
SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (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 national 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 patent 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). 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, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Romania, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and the United Kingdom.” SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 7 1 Scope This standard is a part of the 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 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 common 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 handbook”. This standard may be tailored for the specific characteristic and constrains of a space project in conformance with ECSS-S-ST-00.
SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 8 2 Normative references The following normative documents contain provisions which, through reference in this text, 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 normative 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 ECSS-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
SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 9 3 Terms, definitions 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 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 imparted 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 particles 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 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, SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 10 but dose equivalent at 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 particle 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 destruction 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 component 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 as the microscopic cross-section. Other related definition is the macroscopic cross section, defines as the probability of an interaction per unit path-length of the particle in a material. SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 11 3.2.11 directional dose equivalent
dose at a point equivalent to the one produced by the corresponding expanded radiation field in the ICRU sphere at a specific depth d on a radius on a specified direction NOTE 1 It is normally expressed as H′(d, ), where d is the specific depth used in its definition, in mm, and
is the direction.
NOTE 2 H′(d-penetrating radiation
where a reference depth of 0,07 mm is usually used and the quantity denoted H′(0,07,
3.2.12 displacement damage crystal structure damage caused when particles lose energy by elastic or inelastic collisions in a material 3.2.13 dose quantity of radiation delivered at a position NOTE 1 In its broadest sense this can include the flux of particles, but in the context of space energetic particle radiation effects, it usually refers to the energy absorbed locally per unit mass as a result of radiation exposure. NOTE 2 If “dose” is used unqualified, it refers to both ionising and non-ionising dose. Non-ionising dose can be quantified either through energy deposition via displacement damage or damage-equivalent fluence (see Clause 8). 3.2.14 dose equivalent absorbed dose at a point in tissue which is weighted by quality factors which are related to the LET distribution of the radiation at that point 3.2.15 dose rate rate at which radiation is delivered per unit time 3.2.16 effective dose sum of the equivalent doses for all irradiated tissues or organs, each weighted by its own value of tissue weighting factor NOTE 1 It is normally represented by E, and in accordance with the definition it is calculated with the equation below, and the wT is specified in the ICRP-92 standard [RDH.22]: ∑⋅=TTHwE
(1) For further discussion on E, see ECSS-E-HB-10-12 Section 10.2.2. SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 12 NOTE 2 Effective dose, like organ equivalent dose, is measured in units of sievert, Sv. Occasionally this use of the same unit for different quantities can give rise to confusion. 3.2.17 energetic particle particle which, in the context of space systems radiation effects, can penetrate outer surfaces of spacecraft 3.2.18 equivalent dose See 3.2.41 (organ equivalent dose) 3.2.19 equivalent fluence quantity which represents the damage at different energies and from different species by a fluence of monoenergetic particles of a single species NOTE 1 These are usually derived through testing. NOTE 2 Damage coefficients are used to scale the effect caused by particles to the damage caused by a standard particle and energy. 3.2.20 extrapolated range range determined by extrapolating the line of maximum gradient in the intensity curve until it reaches zero intensity 3.2.21 Firsov scattering the reflection of fast ions from a dense medium at glancing angles NOTE
See references [2]. 3.2.22 fluence time-integration of flux NOTE
It is normally represented by
3.2.23 flux number of particles crossing a surface at right angles to the particle direction, per unit area per unit time 3.2.24 flux number of particles crossing a sphere of unit cross-sectional area (i.e. of radius 1/π) per unit time NOTE 1 For arbitrary angular distributions, it is normally known as omnidirectional flux. NOTE 2 Flux is often expressed in “integral form” as particles per unit time (e.g. electrons cm-2 s-1) above a certain energy threshold. NOTE 3 The directional flux is the differential with respect to solid angle (e.g. particles-cm-2steradian-1s-1) while the “differential” flux is SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 13 differential with respect to energy (e.g. particles-cm-2MeV-1s-1). In some cases fluxes are treated as a differential with respect to linear energy transfer rather than energy. 3.2.25 ICRU sphere sphere of 30 cm diameter made of ICRU soft tissue NOTE
This definition is provided by the International Commission of Radiation Units and Measurements Report 33 [12]. 3.2.26 ICRU Soft Tissue tissue equivalent material with a density of 1 g/cm3 and a mass composition of 76,2 % oxygen, 11,1 % carbon, 10,1 % hydrogen and 2,6 % nitrogen. NOTE
This definition is provided in the ICRU Report 33 [12].
3.2.27 ionising dose amount of energy per unit mass transferred by particles to a target material in the form of ionisation and excitation 3.2.28 ionising radiation transfer of energy by means of particles where the particle has sufficient energy to remove electrons, or undergo elastic or inelastic interactions with nuclei (including displacement of atoms), and in the context of this standard includes photons in the X-ray energy band and above 3.2.29 isotropic property of a distribution of particles where the flux is constant over all directions 3.2.30 L or L-shell parameter of the geomagnetic field often used to describe positions in near-Earth space NOTE
L or L-shell has a complicated derivation based on an invariant of the motion of charged particles in the terrestrial magnetic field. However it is useful in defining plasma regimes within the magnetosphere because, for a dipole magnetic field, it is equal to the geocentric altitude in Earth-radii of the local magnetic field line where it crosses the equator. 3.2.31 linear energy transfer (LET) rate of energy deposited through ionisation from a slowing energetic particle with distance travelled in matter, the energy being imparted to the material NOTE 1 LET is normally used to describe the ionisation track caused due to the passage of an ion. LET SIST EN 16603-10-12:2014
EN 16603-10-12:2014 (E) 14 is material dependent and is also a function of particle energy and charge. For ions involved in space radiation effects, it increases with decreasing energy (it also increases at high energies, beyond the minimum ionising energy). LET allows different ions to be considered together by simply representing the ion environment as the summation of the fluxes of all ions as functions of their LETs. This simplifies single-event upset calculation. The rate of energy loss of a particle, which also includes emitted secondary radiations, is the stopping power. NOTE 2 LET is not equal to (but is often approximated to) particle electronic stopping power, which is the energy loss due to ionisation and excitation per unit pathlength. 3.2.32 LET Threshold minimum LET that a particle should have to cause a SEE in a circuit when going through a device sensitive volume 3.2.33 margin factor or difference between the design environment specification for a device or product and the environment at which unacceptable behaviour occurs 3.2.34 mean organ absorbed dose energy absorbed by an organ due to ionising radiation divided by its mas
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