EN 62387:2016
(Main)Radiation protection instrumentation - Passive integrating dosimetry systems for individual, workplace and environmental monitoring of photon and beta radiation
Radiation protection instrumentation - Passive integrating dosimetry systems for individual, workplace and environmental monitoring of photon and beta radiation
IEC 62387:2012 applies to all kinds of passive dosimetry systems that are used for measuring the personal dose equivalent (for whole body dosimetry), the personal dose equivalent (for eye lens dosimetry), the personal dose equivalent (for both whole body and extremity dosimetry), the ambient dose equivalent (for environmental dosimetry), or the directional dose equivalent (for environmental dosimetry). This standard applies to dosimetry systems that measure external photon and/or beta radiation in the dose range between 0,01 mSv and 10 Sv and in wide energy ranges. The dosimetry systems usually use electronic devices for the data evaluation and thus are often computer controlled.
Strahlenschutz-Messgeräte - Passive integrierende Dosimetriesysteme zur Personen-, Arbeitsplatz- und Umgebungsüberwachung auf Photonen- und Betastrahlung
Instrumentation pour la radioprotection - Systèmes dosimétriques intégrés passifs pour la surveillance de l’individu, du lieu de travail et de l'environnement des rayonnements photoniques et bêta
La CEI 62387:2012 s'applique à toutes sortes de systèmes dosimétriques passifs utilisés pour la mesure des équivalents de dose individuels (pour la dosimétrie du corps entier), des équivalents de dose individuels (pour la dosimétrie des cristallins), des équivalents de dose individuels (pour la dosimétrie du corps entier et pour la dosimétrie d'extrémités), de l'équivalent de dose ambiant (pour la dosimétrie de l'environnement), ou de l'équivalent de dose directionnel (pour la dosimétrie de l'environnement). La présente Norme s'applique aux systèmes dosimétriques qui mesurent les rayonnements photoniques et/ou bêta externes dans le domaine de dose allant de 0,01 mSv à 10 Sv et dans de vastes domaines d'énergie. Les systèmes dosimétriques utilisent habituellement des dispositifs électroniques pour l'évaluation des données et sont donc souvent commandés par ordinateur.
Instrumenti za zaščito pred sevanjem - Pasivni integrirni dozimetrijski sistemi za okoljsko in osebno nadzorovanje - 1. del: Splošne značilnosti in tehnične zahteve
IEC 62387:2012 se uporablja za vse vrste pasivnih dozimetrijskih sistemov za merjenje osebnih ekvivalentnih odmerkov (za dozimetrijo celega telesa), osebnih ekvivalentnih odmerkov (za dozimetrijo očesne leče), osebnih ekvivalentnih odmerkov (za dozimetrijo celotnega telesa in okončin), okoljskih ekvivalentnih odmerkov (za okoljsko dozimetrijo) ali usmerjenih ekvivalentnih odmerkov (za okoljsko dozimetrijo). Ta standard se uporablja za dozimetrijske sisteme, ki merijo zunanje fotonsko in/ali beta sevanje v razponu odmerkov med 0,01 mSv in 10 Sv ter v širših energetskih razponih. Dozimetrijski sistemi so običajno elektronski elementi za vrednotenje podatkov in so tako pogosto računalniško nadzorovani.
General Information
- Status
- Withdrawn
- Publication Date
- 04-Feb-2016
- Withdrawal Date
- 03-Jan-2019
- Technical Committee
- CLC/TC 45B - Radiation protection instrumentation
- Drafting Committee
- IEC/SC 45B - IEC_SC_45B
- Current Stage
- 9960 - Withdrawal effective - Withdrawal
- Start Date
- 21-Mar-2023
- Completion Date
- 21-Jan-2026
Relations
- Effective Date
- 28-Jan-2023
- Effective Date
- 18-Oct-2022
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Frequently Asked Questions
EN 62387:2016 is a standard published by CLC. Its full title is "Radiation protection instrumentation - Passive integrating dosimetry systems for individual, workplace and environmental monitoring of photon and beta radiation". This standard covers: IEC 62387:2012 applies to all kinds of passive dosimetry systems that are used for measuring the personal dose equivalent (for whole body dosimetry), the personal dose equivalent (for eye lens dosimetry), the personal dose equivalent (for both whole body and extremity dosimetry), the ambient dose equivalent (for environmental dosimetry), or the directional dose equivalent (for environmental dosimetry). This standard applies to dosimetry systems that measure external photon and/or beta radiation in the dose range between 0,01 mSv and 10 Sv and in wide energy ranges. The dosimetry systems usually use electronic devices for the data evaluation and thus are often computer controlled.
IEC 62387:2012 applies to all kinds of passive dosimetry systems that are used for measuring the personal dose equivalent (for whole body dosimetry), the personal dose equivalent (for eye lens dosimetry), the personal dose equivalent (for both whole body and extremity dosimetry), the ambient dose equivalent (for environmental dosimetry), or the directional dose equivalent (for environmental dosimetry). This standard applies to dosimetry systems that measure external photon and/or beta radiation in the dose range between 0,01 mSv and 10 Sv and in wide energy ranges. The dosimetry systems usually use electronic devices for the data evaluation and thus are often computer controlled.
EN 62387:2016 is classified under the following ICS (International Classification for Standards) categories: 13.280 - Radiation protection. The ICS classification helps identify the subject area and facilitates finding related standards.
EN 62387:2016 has the following relationships with other standards: It is inter standard links to EN 62387-1:2012, EN IEC 62387:2022. Understanding these relationships helps ensure you are using the most current and applicable version of the standard.
EN 62387:2016 is available in PDF format for immediate download after purchase. The document can be added to your cart and obtained through the secure checkout process. Digital delivery ensures instant access to the complete standard document.
Standards Content (Sample)
SLOVENSKI STANDARD
01-april-2016
1DGRPHãþD
SIST EN 62387-1:2012
,QVWUXPHQWL]D]DãþLWRSUHGVHYDQMHP3DVLYQLLQWHJULUQLGR]LPHWULMVNLVLVWHPL]D
RNROMVNRLQRVHEQRQDG]RURYDQMHGHO6SORãQH]QDþLOQRVWLLQWHKQLþQH]DKWHYH
Radiation protection instrumentation - Passive integrating dosimetry systems for
personal and environmental monitoring of photon and beta radiation
Instrumentation pour la radioprotection - Systèmes dosimétriques intégrés passifs pour
la surveillance de l’individu et de l'environnement des rayonnements photoniques et bêta
Ta slovenski standard je istoveten z: EN 62387:2016
ICS:
13.280 Varstvo pred sevanjem Radiation protection
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.
EUROPEAN STANDARD EN 62387
NORME EUROPÉENNE
EUROPÄISCHE NORM
February 2016
ICS 13.280 Supersedes EN 62387-1:2012
English Version
Radiation protection instrumentation - Passive integrating
dosimetry systems for individual, workplace and environmental
monitoring of photon and beta radiation
(IEC 62387:2012 , modified)
Instrumentation pour la radioprotection - Systèmes Strahlenschutz-Messgeräte - Passive integrierende
dosimétriques intégrés passifs pour la surveillance de Dosimetriesysteme zur Personen-, Arbeitsplatz- und
l'individu et de l'environnement des rayonnements Umgebungsüberwachung auf Photonen- und Betastrahlung
photoniques et bêta (IEC 62387:2012 , modifiziert)
(IEC 62387:2012 , modifiée)
This European Standard was approved by CENELEC on 2016-01-04. 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 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 CENELEC member into its own language and notified to the CEN-CENELEC Management Centre has the
same status as the official versions.
CENELEC members are the national electrotechnical committees of Austria, Belgium, Bulgaria, Croatia, Cyprus, the Czech Republic,
Denmark, Estonia, Finland, Former Yugoslav Republic of Macedonia, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia,
Lithuania, Luxembourg, Malta, the Netherlands, Norway, Poland, Portugal, Romania, Slovakia, Slovenia, Spain, Sweden, Switzerland,
Turkey and the United Kingdom.
European Committee for Electrotechnical Standardization
Comité Européen de Normalisation Electrotechnique
Europäisches Komitee für Elektrotechnische Normung
CEN-CENELEC Management Centre: Avenue Marnix 17, B-1000 Brussels
© 2016 CENELEC All rights of exploitation in any form and by any means reserved worldwide for CENELEC Members.
Ref. No. EN 62387:2016 E
Contents
1 Modification to the title . 4
2 Modification to the Scope . 4
3 Modification to Clause 2 . 4
4 Modification to Clause 3 . 5
5 Modification to Clause 6 . 5
6 Modification to 7.6 . 6
7 Modification to 11.5.1.2 . 6
8 Modification to 11.5.2.2 . 6
9 Modification to 11.6.1.2 . 6
10 Modification to 11.6.2.1 . 6
11 Modification to 11.6.2.2 . 7
12 Modification to 11.6.2.3 . 7
13 Modification to 11.7.1.2 . 8
14 Modification to 11.8 . 8
15 Modification to 11.8.1 . 8
16 Modification to 11.8.2 . 9
17 Modification to 11.8.3 . 9
18 Modification to 13.1.2 . 9
19 Modification to 13.2.1 . 9
20 Modification to 13.2.4 . 9
21 Modification to 13.3.1 . 9
22 Modification to 13.3.4 . 10
23 Modification to 13.4: . 10
24 Modification to 13.4.2 . 10
25 Modification to 13.4.3 . 10
26 Modification to 13.4.4 . 11
27 Modification to 13.6.1 . 11
28 Modification to 13.6.4 . 11
29 Modification to 13.7.2 . 11
30 Modification to 13.7.3 . 11
31 Modification to 13.7.4 . 11
32 Modification to 13.8.3 . 12
33 Modification to 13.8.4 . 12
34 Modification to 13.9.4 . 12
35 Modification to 14.2 . 12
36 Modification to 14.3 . 12
37 Modification to 15.2.2 . 13
38 Modification to tables. 14
39 Modification to Annex C . 23
40 Modification to Annex E . 24
41 Modification to Annex H . 24
42 Modification to Bibliography . 24
European foreword
This document (EN 62387:2016) consists of the text of IEC 62387:2012 prepared by IEC/SC 45B,
"Radiation protection instrumentation", of IEC/TC 45, "Nuclear instrumentation" together with
the common modifications prepared by CLC/TC 45B, "Radiation protection instrumentation".
The following dates are fixed:
(dop) 2017-01-04
• latest date by which this document has to be
implemented
at national level by publication of an identical
national standard or by endorsement
• latest date by which the national standards conflicting (dow) 2019-01-04
with this document have to be withdrawn
This document supersedes EN 62387-1:2012.
Clauses, subclauses, notes, tables, figures and annexes which are additional to those in
IEC 62387:2012 are prefixed “Z”.
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. CENELEC [and/or CEN] shall not be held responsible for identifying any or all such
patent rights.
Endorsement notice
The text of the International Standard IEC 62387:2012 was approved by CENELEC as a
European Standard with agreed common modifications.
COMMON MODIFICATIONS
1 Modification to the title
The title of the standard has been modified to read:
Radiation protection instrumentation – Passive integrating dosimetry systems for individual,
workplace and environmental monitoring of photon and beta radiation
2 Modification to the Scope
Delete NOTE 1.
3 Modification to Clause 2
Replace by
The following documents, in whole or in part, are normatively referenced in this document and
are indispensable for its application. For dated references, only the edition cited applies. For
undated references, the latest edition of the referenced document (including any
amendments) applies.
EN 61000-4-2, Electromagnetic compatibility (EMC) – Part 4-2: Testing and measurement
techniques – Electrostatic discharge immunity test (IEC 61000-4-2)
EN 61000-4-3, Electromagnetic compatibility (EMC) – Part 4-3: Testing and measurement
techniques – Radiated, radio-frequency, electromagnetic field immunity test (IEC 61000-4-3)
EN 61000-4-4, Electromagnetic compatibility (EMC) – Part 4-4: Testing and measurement
techniques – Electrical fast transient/burst immunity test (IEC 61000-4-4)
EN 61000-4-5, Electromagnetic compatibility (EMC) – Part 4-5: Testing and measurement
techniques – Surge immunity test (IEC 61000-4-5)
EN 61000-4-6, Electromagnetic compatibility (EMC) – Part 4-6: Testing and measurement
techniques – Immunity to conducted disturbances, induced by radio-frequency fields
(IEC 61000-4-6)
EN 61000-4-8, Electromagnetic compatibility (EMC) – Part 4-8: Testing and measurement
techniques – Power frequency magnetic field immunity test (IEC 61000-4-8)
EN 61000-4-11, Electromagnetic compatibility (EMC) – Part 4-11: Testing and measurement
techniques – Voltage dips, short interruptions and voltage variations immunity tests
(IEC 61000-4-11)
EN 61000-6-2, Electromagnetic compatibility (EMC) – Part 6-2: Generic standards – Immunity
for industrial environments (IEC 61000-6-2)
ISO 4037 (all parts), X and gamma reference radiation for calibrating dosemeters and
doserate meters and for determining their response as a function of photon energy
ISO 4037-3:1999, X and gamma reference radiation for calibrating dosemeters and doserate
meters and for determining their response as a function of photon energy – Part 3: Calibration
of area and personal dosemeters and the measurement of their response as a function of
energy and angle of incidence
ISO 6980 (all parts), Nuclear energy – Reference beta-particle radiation
ISO 6980-3, Nuclear energy – Reference beta-particle radiation – Part 3: Calibration of area
and personal dosemeters and the determination of their response as a function of beta
radiation energy and angle of incidence
ISO 8529 (all parts), Reference neutron radiations
ISO/IEC Guide 98-3:2008, Uncertainty of measurement – Part 3: Guide to the expression of
uncertainty in measurement (GUM:1995)
4 Modification to Clause 3
Add the following terms and definitions:
3.Z1
area monitoring
monitoring in which a workplace or an area in the environment is monitored by taking dose
(rate) measurements
Note 1 to entry: Area monitoring is performed in terms of H'(0.07) or H*(10).
Note 2 to entry: Definition orientated at ICRP 103 and ICRP 116.
3.Z2
workplace monitoring
area monitoring using dose (rate) measurements made in the working environment
Note 1 to entry: Usually contrasted with individual monitoring.
Note 2 to entry: Workplace monitoring is performed in terms of H'(0.07) or H*(10).
3.Z3
environmental monitoring
area monitoring by the measurement of external dose (rate) in the environment
Note 1 to entry: Environmental monitoring is performed in terms of H'(0.07) or H*(10).
3.Z4
individual monitoring
monitoring using dose (rate) measurements by equipment worn by individual workers, or
measurements of quantities of radioactive material in or on their bodies
Note 1 to entry: Also called personal monitoring. Usually contrasted with workplace monitoring.
Note 2 to entry: Individual monitoring is performed in terms of H (0.07), H (3) or H (10).
p p p
[SOURCE: IAEA glossary, modified – “dose (rate)” has been added and Note 2 to entry has
been added]
5 Modification to Clause 6
In the following sentence, replace "Table 9 to 11" by "Table 13 to Table 15":
Details for some of the entries in Tables 8 to 12 (at the end of the document) are given in the
further Tables 13 to 15 (at the end of the document).
6 Modification to 7.6
Add the following note:
NOTE Z1 Further details regarding the model function and the determination of uncertainty in measurement
are given in IEC/TR 62461.
7 Modification to 11.5.1.2
Add the following NOTE afte NOTE 1:
NOTE Z1 For personal dose quantities: Also take into account section 8.4 f) and line 11 of Table 8.
Modify the following paragraph as follows:
For H*(10) dosemeters and a = 90°, the dosemeter shall be rotated about its reference
direction during the irradiation. If no rotation is possible, eight subsequent irradiations with
different polar angles in steps of 45° can be done irradiating the same dosemeter. As a is 90°,
the reference direction is orientated perpendicular to the radiation beam. The rotation may be
omitted if the dosemeter has a holder defining the orientation with respect to the expected
direction of radiation incidence.
8 Modification to 11.5.2.2
Replace the last sentence by:
For this radiation quality, the mean indicated value G and the standard deviation s shall be
determined.
9 Modification to 11.6.1.2
Add the following NOTE after NOTE 1:
NOTE Z1 Also take into account section 8.4 f) and line 11 of Table 9.
10 Modification to 11.6.2.1
Replace the subclause by:
Requirement A: The variation of the relative response due to a change of the radiation energy
and angle of incidence within the rated ranges for beta radiation shall not exceed the values
given in line 10 of Table 9.
Requirement B: As the dosemeter is intended to measure H (3), the indicated value due to
p
beta radiation with energies up the energy equivalent of Kr shall be less than 0,1·H (0,07)
p
(see line 10 of Table 9).
11 Modification to 11.6.2.2
Replace the subclause by:
For requirement A:
The following reference radiation qualities specified in ISO 6980 shall be used:
90 90 106 106
Sr/ Y (mean energy ≈ 0,8 MeV); Ru/ Rh (mean energy ≈ 1,2 MeV).
As long as no conversion coefficients for the conversion from personal absorbed dose in
0,07 mm depth, D (0,07), to the personal dose equivalent, H (3), are available in ISO 6980-3,
p p
the values given in Annex G shall be used.
The tests shall be performed for those radiation qualities whose mean energy falls in the rated
range of energy. Angles of incidence shall be: a = 0°, a = ± 45°, a = ± 60° and a = ± 75° if
included in the rated range of angle of incidence in two perpendicular planes containing the
reference direction through the reference point of the dosemeter.
For every radiation quality, the mean indicated value G and the standard deviation s shall
i,A i,A
be determined.
NOTE 1 Details of the reference radiation and the calibration procedure are given in ISO 6980.
NOTE 2 i refers to a group of dosemeters irradiated equally, for example Sr-90, 60° (from above). That means,
the different directions (horizontal from the right and left; vertical from above and the bottom) for one angle of
incidence are not averaged.
NOTE 3 For an H (3) dosemeter, at each of the two lowest radiation energies, at least five groups of dosemeters
p
are irradiated: one at 0° and four at 60°.
For requrirement B:
For this test, the dosemeter shall be placed on a phantom as required (see 5.1.5). Expose
n (≥ 4) dosemeters at 0° angle of incidence to beta reference radiation specified in ISO 6980:
– Kr (mean energy ≈ 0,24 MeV).
The dose equivalent shall be at least H (0,07) = 10 mSv = C.
p
NOTE Z1 Details of the reference radiation and the calibration procedure are given in ISO 6980.
For this radiation quality, the mean indicated value G and the standard deviation s shall be
B B
determined.
12 Modification to 11.6.2.3
Replace the subclause by:
For requirement A:
G C
i,A r,0,A
If, for every radiation quality, the inequality r − U ≤ ±U ⋅ ≤ r +U
min C,com com max C,com
G C
r,0,A i,A
is valid, then requirement A of 11.6.2.1 is considered to be met. The values for r and r
min max
are given in line 10 of Table 9.
U is calculated according to Equation (A.5), Example 2. U is the combined relative
com C,com
C
r,0
2 2
expanded uncertainty of : U = U +U with the relative expanded
C,com C,rel; r,0 C,rel; i
C
i
uncertainties U and U of the conventional true values C and C for the different
C,rel; r,0 C,rel; i r,0 i
radiation qualities, respectively. In case U and U are correlated, this shall be
C,rel; r,0 C,rel; i
taken into account. For U , see 5.2.2.
C,rel
For requirement B:
If G + U ≤ 0,1·C is valid, then requirement B of 11.6.2.1 is considered to be met.
B m
is calculated according to Equation (A.3).
U
m
13 Modification to 11.7.1.2
Add the following NOTE after NOTE 1:
NOTE Z1 For personal dose quantities: Also take into account section 8.4 f) and line 11 of Table 10.
Modify the following paragraph as follows:
For H ’(0,07) dosemeters and a = 90°, the dosemeter shall be rotated about its reference
direction during the irradiation. If no rotation is possible, eight subsequent irradiations with
different polar angles in steps of 45° can be done irradiating the same dosemeter. As a is 90°,
the reference direction is orientated perpendicular to the radiation beam. The rotation may be
omitted if the dosemeter has a holder defining the orientation with respect to the expected
direction of radiation incidence.
14 Modification to 11.8
Modify the title to read "Over indication due to radiation incident from the side of an
H (10), H (3) or H (0,07) dosemeter"
p p p
15 Modification to 11.8.1
Replace the subclause by:
If the dosemeter is irradiated free in air from the side (a to 180°–a ), the indicated value
max max
shall not exceed 3 times the indicated value resulting from an irradiation free in air with the
same radiation quality from the front (0°). This shall apply to all radiation energies within the
rated range of energy.
NOTE 1 This requirement prevents the acceptance of a detector with a high atomic number material without
sufficient shielding which may cause a large over response from the side.
NOTE 2 If a = 60°, this means an irradiation from 60° to 120°.
max
NOTE Z1 No lower limit is required as the conventional true value is zero for beta radiation and for low energy
photon radiation.
16 Modification to 11.8.2
Modify the following paragraph as follows:
Further groups: Irradiations shall be performed at the angle of incidences β corresponding
to the “weak points”. The azimuthal angle of incidence shall be varied
during the irradiation between a and 180°–a in steps of 15°
max max
including 90°.
Separate groups shall be irradiated separately for every polar angle β (i.e.
for every “weak point”).
Modify the NOTE as follows:
NOTE In case of a = 60°, the irradiation of each badge is performed in five equivalent fractions at 75°, 90°,
max
and 105°.
17 Modification to 11.8.3
Replace the subclause by:
If, for every polar angle examined in accordance with 11.8.2, the inequality
G
a to 180°−a
max max
+U ≤ 3 is valid, then the requirement of 11.8.1 is considered to be met.
com
G
0°
U is calculated according to Equation (A.5), Example 2.
com
18 Modification to 13.1.2
Add the following sentence at the beginning of the subclause:
As the tests described in this clause are performed using rather low doses such as 7·H the
low
consideration of the natural background radiation is of special importance, see 5.2.4.
19 Modification to 13.2.1
Replace the subclause by:
The influence quantity dealt with in 13.2 is assumed to be of type F or of type S.
20 Modification to 13.2.4
Modify the last sentence of the subclause as follows:
U is calculated according to Equation (A.5), Example 1 or Example 2, for differences or
com
ratios, respectively.
21 Modification to 13.3.1
Replace the subclause by:
The influence quantity dealt with in 13.3 is assumed to be of type F or of type S.
22 Modification to 13.3.4
Modify the last sentence of the subclause as follows:
U is calculated according to Equation (A.5), Example 1 or Example 2, for differences or
com
ratios, respectively.
23 Modification to 13.4:
Modify the title of 13.4 to read "Dose build-up, fading and self-irradiation (dosemeter)"
24 Modification to 13.4.2
Replace the subclause by:
The relative response and the deviation due to dose build up, fading and self-irradiation shall
not exceed the values given in line 3 of Table 13.
25 Modification to 13.4.3
Replace the subclause by:
For this test, three groups of dosemeters shall be used.
Groups 1 to 3 consisting of n (≥ 6) dosemeters shall be exposed to a reference source, see
13.1.2. The irradiations shall be performed at different times so that all readings take place at
the same time (in order to exclude possible effects due to reader instabilities during the test).
Further information regarding the method of test are given in 13.1.2.
Treatment of the three groups after the irradiation:
Group 1 shall be read out 24 hours (or as soon as possible) after the irradiation.
Group 2, reference group, shall be read out one week after the irradiation.
Group 3 shall be read out after the maximum rated measurement time t after the
max
irradiation.
For every group, the mean indicated value G and the standard deviation s shall be
i i
determined.
26 Modification to 13.4.4
Replace the subclause by:
G
i
If for groups 1 to 3 the inequality r ≤ ±U ≤ r (for type F influence quantities) or
min com max
G
the inequality G − G ± U ≤ D (for type S influence quantities) is valid, then the
i 2 com max
requirements of 13.4.2 are considered to be met. The values for r , r , and D are
min max max
given in line 3 of Table 13.
U and U are calculated according to Equation (A.5), Example 1 or Example 2, for
com m
differences or ratios, respectively, and Equation (A.3), respectively.
27 Modification to 13.6.1
Replace the subclause by:
The influence quantity dealt with in 13.6 (time) is assumed to be of type F or of type S.
28 Modification to 13.6.4
Replace the last sentence of the subclause by:
U is calculated according to Equation (A.5), Example 1 or Example 2, for differences or
com
ratios, respectively.
29 Modification to 13.7.2
Replace the last sentence of the subclause by:
In case it can be made sure by physical reasons that temperature does not have a significant
effect on the indicated value then this test can be omitted.
30 Modification to 13.7.3
Replace the second sentence of the subclause by:
For this test, two groups of n (≥ 6) dosemeters shall be exposed to a reference source, see
13.1.2.
31 Modification to 13.7.4
Replace the last sentence of the subclause by:
U is calculated according to Equation (A.5), Example 1 or Example 2, for differences or
com
ratios, respectively.
32 Modification to 13.8.3
Replace the first sentence of the subclause by:
For this test, two groups of n (≥ 6) dosemeters shall be exposed to a reference source, see
13.1.2.
33 Modification to 13.8.4
Replace the last sentence of the subclause by:
U is calculated according to Equation (A.5), Example 1 or Example 2, for differences or
com
ratios, respectively.
34 Modification to 13.9.4
Replace the last sentence of the subclause by:
U is calculated according to Equation (A.5), Example 1 or Example 2, for differences or
com
ratios, respectively.
35 Modification to 14.2
Replace the subclause by:
The absolute value of the deviation due to electromagnetic disturbances shall not exceed
0,7·H for every single influence quantity, see Table 14. Exception: The absolute value of
low
the deviation may be larger than 0,7·H for one indicated value, if the dosimetry system
low
delivers an error message assigning that this value is faulty. In addition, the dosimetry system
shall not lose more than one indicated value, see 10.5.
For all influence quantities, the mandatory ranges are taken from IEC 61000-6-2.
The tests in lines 4, 5, and 7 of Table 14 need not to be done for readers for which the
manufacturer declares that either the respective influence quantity does not affect the
indicated value by more than 0,7·H during readout of dosemeters or the effect is
low
recognized and accompanied by an error message (at most one, see above) or the effect is
corrected for (for example by means of software). This declaration shall contain the necessary
evidence. This evidence can be a physical reason why the device is not affected by the
electromagnetic disturbance or why the electromagnetic disturbance is not present. This
evidence has to be stated for each electromagnetic disturbance separately. One example is,
that no mobile phones are allowed in the room of the reader.
36 Modification to 14.3
Replace the subclause by:
As the tests described in this clause are performed using rather low doses such as 7·H the
low
consideration of the natural background radiation is of special importance, see 5.2.4.
For the test according to lines 1 to 6 of Table 14 seven groups of n (≥ 10) dosemeters and for
the test according to line 7 of Table 14 one group of n (≥ 13) dosemeters shall be exposed to
a reference source with a dose equivalent of 7·H . For those influence quantities for which a
low
declaration of the manufacturer is available, see 14.2, no dosemeters need to be irradiated.
Group 1, reference group: no electromagnetic influences shall be present. To assure this,
appropriate filters, shieldings and so on shall be applied.
Groups 2, 6 and 8: in case the dosemeters contain any electric parts that may be sensitive to
electromagnetic disturbances (for example a DIS dosemeter), the dosemeters shall be
exposed to the influence quantities according to lines 1, 5 and 7 of Table 14 prior to their
readout. The radio frequency radiation shall be applied with the frequencies stated in footnote
d to Table 14.
Group 1 shall be read out without any electromagnetic influences.
Groups 2 to 8 shall be read out while the different electromagnetic influences are applied to
the reader in accordance with the standards of the IEC 61000-4 series as given in Table 14.
Each electromagnetic influence shall be applied for the duration of the readout of one
dosemeter. If possible, the output of the reader (for example glow curve) shall be observed.
Without error message, no abnormal characteristics (for example spikes in a glow curve that
cause non-negligible doses) shall occur.
For every group, the mean indicated value G and the standard deviation s shall be
i
i
determined. In case any indicated values were marked by the dosimetry system as faulty,
these values shall be excluded from the determination of G and s .
i i
37 Modification to 15.2.2
Add the following sentence at the beginning of the clause:
As the tests described in this clause are performed using rather low doses such as 7·H the
low
consideration of the natural background radiation is of special importance, see 5.2.4.
38 Modification to tables
Replace Table 6 by the following table:
Table 6 – Symbols
Symbol Meaning Unit
a Angle of radiation incidence Degrees
Maximum value of the rated range of the angle of radiation incidence Degrees
a
max
b Number of signals of one dosemeter that are used to evaluate the indicated dose —
value
C Conventional true dose value Sv
C Conventional true dose value of irradiation group i Sv
i
C Conventional true value of (delivered) dose equivalent for irradiation condition K Sv
K
C Conventional true value of (delivered) dose equivalent for irradiation condition L Sv
L
C Conventional true value of (delivered) dose equivalent under reference conditions: Sv
r
that means, all influence quantities have their reference value, except the value of the
dose equivalent is different from its reference condition: C ≠ C
r r,0
C As C but only for reference dose equivalent, see Table 2, line 1 Sv
r,0 r
∆G Change in indication caused by subsequent and mixed exposure, see 11.9 Sv
d Depth in ICRU 4-element or soft tissue. Recommended depths are 10 mm, 3 mm, and m
0,07 mm
D Deviation Sv
D Deviation due to electromagnetic disturbances Sv
EMC
D Maximum permitted variation of deviation due to an influence quantity Sv
max
D Deviation due to mechanical disturbances Sv
mech
D Deviation due to influence quantity no. p of type S; p = 1.l Sv
p
E
Beta energy keV or MeV
beta
E Photon energy keV or MeV
ph
f(S S ) = Function representing the evaluation algorithm inside the dosimetry system to Sv
1,., b
f(S ) evaluate the indicated value
g
g Designator for a specific signal delivered from one dosemeter; g = 1.b —
G Indicated value Sv
Mean indicated value of group i Sv
G
i
Mean indicated value of group i prime (background indications subtracted) Sv
G '
i
G Indicated value of the j-th dosemeter of several dosemeters irradiated equally; j = 1.n Sv
j
G Indicated value of the j-th dosemeter of group i Sv
j,i
G Indicated value due to a single irradiation with C Sv
K K
G
Indicated value due to a combined irradiation with C + C Sv
K+L
K L
G Indicated value due to a single irradiation with C Sv
L L
G Indicated value of a dosemeter irradiated with C Sv
r r
G Indicated value of a dosemeter irradiated with C Sv
r,0 r,0
Conversion coefficient from air kerma to the personal dose equivalent at a depth d for Sv
h (d;R,a)
pK
the radiation series R
Conversion coefficient from air kerma to the directional dose equivalent at a depth d Sv
h’ (d;R,a)
K
for the radiation series R
H Synonym for dose equivalent, may be H (10), H (0,07) or H*(10) Sv
p p
H Lower dose limit of the range of measurement Sv
low
H Upper dose limit of the range of measurement Sv
up
H*(10) Ambient dose equivalent at a depth 10 mm Sv
H*(d) Ambient dose equivalent at a depth d Sv
H (0,07) Personal dose equivalent at a depth 0,07 mm Sv
p
H (3) Personal dose equivalent at a depth 3 mm Sv
p
H (10) Personal dose equivalent at a depth 10 mm Sv
p
H (d) Personal dose equivalent at a depth d Sv
p
Table 6 (continued)
Symbol Meaning Unit
i
Designator for a group subjected to a specific influence quantity —
j Designator for a specific dosemeter out of n dosemeters irradiated equally —
k Coverage factor —
K Symbol of radiation condition K, e. g. 3 mSv, N-80 and 60° —
l Number of influence quantities of type S —
L Symbol of radiation condition L, e. g. 4 mSv, S-Co and 0° —
m Number of influence quantities of type F —
M Measured value Sv
n Number of dosemeters in one group that are equally irradiated —
N Pointer to the table entry containing the signals (N’s row) —
N
(Reference) calibration factor —
N Number of rows in the table containing the signals —
max
p Designator for a specific influence quantity of type S out of l type S influence —
quantities
q Designator for a specific influence quantity of type F out of m type F influence —
quantities
r Relative response —
r
Relative response due to energy and angle of incidence —
E,a
r Relative response due to environmental influences —
env
r Maximal permitted value of the relative response due to an influence quantity —
max
r Maximal permitted value of the relative response due to an influence quantity for a —
max,w
mixed irradiation
r
Minimal permitted value of the relative response due to an influence quantity —
min
r Minimal permitted value of the relative response due to an influence quantity for a —
min,w
mixed irradiation
r Relative response due to non-linearity —
n
r Relative response due to influence quantity no. q of type F; q = 1.m —
q
R Symbol of radiation series R, for example, N series or S series —
R Response —
R Reference response —
R Response under reference conditions, except the value of the dose equivalent is —
n
different from reference conditions
s
Standard deviation As quantity
s Standard deviation of group i As quantity
i
S Signal of a detector; from one detector more than one signal can be derived Depending
S Signal number g of a dosemeter; g = 1.b Depending
g
S Signal number g due to the radiation quality K Depending
g,K
S Signal number g due to the radiation quality L Depending
g,L
t Maximum rated measurement time Month
max
t
Students t-factor for n measurements —
n-1
U Expanded uncertainty As quantity
U Expanded uncertainty of a combined quantity of conventional true values. This As quantity
C,com
uncertainty is equivalent to the half-width of the confidence interval about the
combined quantity at a confidence level of 95 %
U Relative expanded uncertainty of the conventional true value —
C,rel
U Expanded uncertainty of a combined quantity. This is equivalent to the half-width of As quantity
com
the confidence interval about the combined quantity at a confidence level of 95 %.
See Annex A, Equation (A.5)
U Expanded uncertainty of a mean value. This is equivalent to the half-width of the As quantity
m
confidence interval about a mean at a confidence level of 95 %
U Relative expanded uncertainty —
rel
V
coefficient of variation As quantity
Replace Table 8 by the following table:
Table 8 – Performance requirements for H (10) dosemeters
p
Main characteristics or
Clause/
mandatory measuring Performance requirement for
Line Characteristic under test Sub-
range or mandatory range the rated range
clause
of influence quantity
1 Capability of the dosimetry Measuring range; influence To be documented by the 7
system quantities; t ; model manufacturer for the type test
max
function
2 Requirements to the design of Dose indication; information To be documented by the 8
the dosimetry system on reader, dosemeter and manufacturer for the type test
evaluation algorithm and checked during type test
3 Effects of radiation not intended Response to thermal Response to be stated by the 8.7
252 252
to be measured neutrons, Cf and Cf manufacturer
(D O-moderated)
4 Instruction manual Information for correct use; To be documented by the 9
information about the manufacturer for the type test
performance of the system and checked during type test
5 Software, data and interfaces Authenticity of the software; To be documented by the 10
correctness and integrity of manufacturer for the type test
data and checked during type test
6 Coefficient of variation, v 15 % 11.2
H < 0,1 mSv
(16 – H/0,1 mSv) %
0,1 mSv ≤ H < 1,1 mSv
5 %
H ≥ 1,1 mSv
7 Relative response due to non- 0,1 mSv ≤ H ≤ 1 Sv –13 % to +18 % 11.3
linearity
8 Overload, after-effects, and 10 times the upper limit of Perception to be off-scale on 11.4
reusability the measuring range: the high end side of the
10·H , however at
measuring range, after-effects
up
maximum 10 Sv. may not cause fault
Reused dosemeters shall measurements and v(H ) shall
low
fulfil the requirements be according to line 6
9 Relative response due to mean 80 keV to 1,25 MeV and For 12 keV ≤ E < 33 keV: 11.5.1
ph
photon radiation energy and
0° to ± 60° from reference r = 0,67 to r = 2,00 and
min max
angle of incidence
direction for 33 keV ≤ E < 65 keV:
ph
r = 0,69 to r = 1,82 and
min max
for E ≥ 65 keV:
ph
r = 0,71 to r = 1,67
min max
10 Relative response due to mean 0,8 MeV Indicated value maximal 10 % of 11.5.2
beta radiation energy H (0,07) dose equivalent
p
11 As in lines 9 and 10 but new See lines 9 and 10, if no See lines 9 and 10, if no 8.4 f)
reference direction opposite to statement by the statement by the manufacturer
that one used manufacturer
12 Radiation incidence from the side Radiation incidence from Indication less than 3 times of 11.8
of the dosemeter 60° to 120° indication due to irradiation free
in air from the front
13 Response to mixed irradiations Irradiation with different Response within ranges of 12
radiation qualities radiation qualities under test
14 Total effect due to environmental Temperature, light, time; See Table 13 13
performance requirements for details, see Table 13
15 Deviation due to electromagnetic See Table 14 See Table 14 14
performance requirements
16 Deviation due to mechanical Drop; 15
± 0,7·H at a dose of
low
performance requirements for details, see Table 15
H = 7 H
low
NOTE The non-symmetrical borders of relative responses r are derived from symmetrical borders of correction
factors (1/r), for example: ± 40 % for 1/r ∈ [0,6 . 1,4] r ∈ [1/1,4 . 1/0,6] = [0,71 . 1,67]
Replace Table 9 by the following table:
Table 9 – Performance requirements for H (3) dosemeters
p
Main characteristics or
Clause/
mandatory measuring Performance requirement for
Line Characteristic under test Sub-
range or mandatory range the rated range
clause
of influence quantity
1 Capability of the dosimetry Measuring range; influence To be documented by the 7
system quantities; t ; model manufacturer for the type test
max
function
2 Requirements to the design of Dose indication; information To be documented by the 8
the dosimetry system on reader, dosemeter and manufacturer for the type test
evaluation algorithm and checked during type test
3 Effects of radiation not intended Response to thermal Response to be stated by the 8.7
252 252
to be measured neutrons, Cf and Cf manufacturer
(D O-moderated)
4 Instruction manual Information for correct use; To be documented by the 9
information about the manufacturer for the type test
performance of the system and checked during type test
5 Software, data and interfaces Authenticity of the software; To be documented by the 10
correctness and integrity of manufacturer for the type test
data and checked during type test
6 Coefficient of variation, v 15 % 11.2
H < 0,3 mSv
(18,75 – H/0,08 mSv) %
0,3 mSv ≤ H < 1,1 mSv
5 %
H ≥ 1,1 mSv
7 Relative response due to non- 0,3 mSv ≤ H ≤ 1 Sv –13 % to +18 % 11.3
linearity
8 Overload, after-effects, and 10 times the upper limit of Perception to be off-scale on 11.4
reusability the measuring range: the high end side of the
10·H , however at measuring range, after-effects
up
maximum 10 Sv. may not cause fault
Reused dosemeters shall measurements and v(H ) shall
low
fulfil the requirements be according to line 6
9 Relative response due to mean 30 keV to 250 keV and r = 0,71 to r = 1,67 11.6.1
min max
photon radiation energy and
0° to ± 60° from reference
angle of incidence
direction
Relative response, r, due to A: r = 0,71 to r = 1,67
10 A: 0,8 MeV and 11.6.2
min max
mean beta radiation energy 0° to ± 60° from reference
B: Indicated value maximal
direction
10 % of H (0,07) dose
p
equivalent
B: 0,24 MeV
11 As in lines 9 and 10 but new See lines 9 and 10, if no See lines 9 and 10, if no 8.4 f)
reference direction opposite to statement by the statement by the manufacturer
that one used manufacturer
12 Radiation incidence from the side Radiation incidence from Indication less than 3 times of 11.8
of the dosemeter 60° to 120° indication due to irradiation free
in air from the front
13 Response to mixed irradiations Irradiation with different Response within ranges of 12
radiation qualities radiation qualities under test
14 Total effect due to environmental Temperature, light, time; See Table 13 13
performance requirements for details, see Table 13
15 Deviation due to electromagnetic See Table 14 See Table 14 14
performance requirements
16 Deviation due to mechanical Drop; 15
± 0,7·H at a dose of
low
performance requirements for details, see Table 15
H = 7 H
low
NOTE The non-symmetrical borders of relative responses r are derived from symmetrical borders of correction
factors (1/r), for example: ± 40 % for 1/r ∈ [0,6 . 1,4] r ∈ [1/1,4 . 1/0,6] = [0,71 . 1,67]
Replace Table 10 by the following table:
Table 10 – Performance requirements for H (0,07) dosemeters
p
Main characteristics or
Clause/
Performance requirement for
mandatory measuring
Line Characteristic under test Sub-
range or mandatory range the rated range
clause
of influence quantity
1 Capability of the dosimetry Measuring range; influence To be documented by the 7
system quantities; t ; model manufacturer for the type test
max
function
2 Requirements to the design of Dose indication; information To be documented by the 8
the dosimetry system on reader, dosemeter and manufacturer for the type test
evaluation algorithm and checked during type test
3 Effects of radiation not intended Response to thermal Response to be stated by the 8.7
252 252
to be measured neutrons, Cf and Cf manufacturer
(D O-moderated)
4 Instruction manual Information for correct use; To be documented by the 9
information about the manufacturer for the type test
performance of the system and checked during type test
5 Software, data and interfaces Authenticity of the software; To be documented by the 10
correctness and integrity of manufacturer for the type test
data and checked
...




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