EN 61526:2007

2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.Radiation protection instrumentation - Measurement of personal dose equivalents Hp(10) and Hp(0,07) for X, gamma, neutron and beta radiations - Direct reading personal dose equivalent meters and monitorsInstrumentation pour la radioprotection - Mesure des équivalents de dose individuels Hp(10) et Hp(0,07) pour les rayonnements X, gamma, neutron et beta - Appareils de mesure a lecture directe et moniteurs de l'équivalent de dose individuelStrahlenschutz-Messgeräte - Messung der Tiefen- und der Oberflächen- Personendosis Hp(10) und Hp(0,07) für Röntgen-, Gamma-, Neutronen- und Betastrahlung - Direkt ablesbare Personendosimeter und -monitoreTa slovenski standard je istoveten z:EN 61526:2007SIST EN 61526:2007en,fr,de17.240Merjenje sevanjaRadiation measurements13.280Varstvo pred sevanjemRadiation protectionICS:SLOVENSKI
STANDARDSIST EN 61526:200701-oktober-2007

EUROPEAN STANDARD EN 61526 NORME EUROPÉENNE
EUROPÄISCHE NORM March 2007
CENELEC European Committee for Electrotechnical Standardization Comité Européen de Normalisation Electrotechnique Europäisches Komitee für Elektrotechnische Normung
Central Secretariat: rue de Stassart 35, B - 1050 Brussels
© 2007 CENELEC -
All rights of exploitation in any form and by any means reserved worldwide for CENELEC members.
Ref. No. EN 61526:2007 E
ICS 13.280
English version
Radiation protection instrumentation -
Measurement of personal dose equivalents Hp(10)
and Hp(0,07) for X, gamma, neutron and beta radiations -
Direct reading personal dose equivalent meters and monitors (IEC 61526:2005, modified)
Instrumentation pour la radioprotection -
Mesure des équivalents de dose individuels Hp(10) et Hp(0,07)
pour les rayonnements X, gamma, neutron et bêta -
Appareils de mesure à lecture directe
et moniteurs de l'équivalent
de dose individuel (CEI 61526:2005, modifiée)
Strahlenschutz-Messgeräte -
Messung der Tiefen- und
der Oberflächen-Personendosis
Hp(10) und Hp(0,07)
für Röntgen-, Gamma-,
Neutronen- und Betastrahlung -
Direkt ablesbare Personendosimeter
und -monitore (IEC 61526:2005, modifiziert)
This European Standard was approved by CENELEC on 2006-10-01. 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 Central Secretariat 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 Central Secretariat has the same status as the official versions.
CENELEC members are the national electrotechnical committees of Austria, Belgium, Bulgaria, Cyprus, the Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, Norway, Poland, Portugal, Romania, Slovakia, Slovenia, Spain, Sweden, Switzerland and the United Kingdom.

Foreword The text of the International Standard IEC 61526:2005, prepared by SC 45B, Radiation protection instrumentation, of IEC TC 45, Nuclear instrumentation, together with the common modifications prepared by the CENELEC BTTF 111-3, Nuclear instrumentation and radiation protection instrumentation, was submitted to the formal vote and was approved by CENELEC as EN 61526 on 2006-10-01. The following dates were fixed: – latest date by which the EN has to be implemented at national level by publication of an identical national standard or by endorsement
(dop)
2007-10-01 – latest date by which the national standards conflicting with the EN have to be withdrawn
(dow)
2009-10-01 Annexes ZA and ZB have been added by CENELEC. __________

– 3 –
Endorsement notice The text of the International Standard IEC 61526:2005 was approved by CENELEC as a European Standard with agreed common modifications as given below. COMMON MODIFICATIONS
Introduction
Modify the second paragraph in order to read:
“. 1,5 MeV is considered in the standard and for neutron radiation, from at least thermal neutrons to 15 MeV.”
In the fourth paragraph replace “10 MeV is” with “10 MeV should be” and replace “10 keV is” with “10 keV should be” .
In the fifth paragraph delete “for which no requirements are given”.
1 Scope and object
In sub-paragraph b) replace “if the radiation can be considered to be continuous” with “and may measure the personal dose equivalent rates )10(pH& and )07,0(pH&”.
In the paragraph below sub-paragraph d), replace “quantities and radiation” with “dose quantities (including the respective dose rates) and radiation”.
Add at the end of the penultimate paragraph: “In addition, usage categories are given in Annex ZA with respect to different measuring capabilities.”
Replace the last sentence of the last paragraph with: “The standard does not apply to dosemeters used for measurement of pulsed radiation where the dose rate in the pulse exceeds the specification such as that emanating from linear accelerators or similar equipment.”.
2 Normative references
Add:
IEC/TR 62461:2006, Radiation protection instrumentation – Determination of uncertainty in measurement
3 Terms and definitions 3.30 reference point of an assembly
Replace “at a point” with “at the point of test”. 3.31 reference response
Replace the whole definition with: reference response R0
response of the assembly under reference conditions to unit reference dose (rate) and is expressed as: r,0t,r,0i,0HHR= where Ht,r,0 is a reference (conventionally true) value of the quantity to be measured for a specified reference radiation under specified reference conditions and Hi,r,o is the respective indicated value.

NOTE 1 The background value may be automatically taken in account by an algorithm included in the measurement system. NOTE 2 The reference response is the reciprocal of the reference calibration factor. 3.33 relative response
Add a note below the equation, reading:
NOTE The reference response R0 is always measured at 0° radiation incidence at the reference energy, see 3.31.
6 General characteristics 6.1 Personal dose equivalent meter classification
Add a note, reading:
NOTE Personal dosemeters are designed for specific applications (see Table ZA.1) so the manufacturers are required to specify the types of radiation, the measuring range, the energy ranges and the ranges of all other influence quantities their dosimeters are designed for (see 14.2). The purchasers may make reference to Table ZA.1 to determine which categories apply to their requirements.
6.6 Effective range of measurement
In the first paragraph, replace “four orders of magnitude” with “the range from 100 µSv to 1 Sv for the measuring quantity Hp(10) and from 1 mSv to 10 Sv for the measuring quantity Hp(0,07)”.
6.7 Rated range of an influence quantity
Replace the first sentence of 6.7 with:
The rated range of any influence quantity has to be stated by the manufacturer in the documentation, it shall cover at least the minimum rated range given in the third column of Tables 3 to 8. Suggestions for extensions are given in Table ZA.1.
6.9 Zero effect and indication due to natural environmental radiation
Replace the headline with “Indication due to zero effect and natural environmental radiation”.
Replace the text of 6.9 with:
For a personal dose meter for Hp(10) from X and gamma radiations the indication due to zero effect and natural environmental radiation shall be given by the manufacturer for an integrating period equivalent to the maximum possible measuring time tmax, for test see 9.4.
NOTE This value is required if measured values of dose equivalents accumulated during several days, for example one month, and measured using different dosemeters should be compared.
6.10 Resettable dose or dose rate alarms
Delete “Resettable” in the headline. 6.10.4 Alarm output
In sub-paragraph b), add “(impulse level for intermittent alarm)” between “The A-weighted sound level” and “shall exceed 80 dBA”.

– 5 –
7 General test procedures 7.3 Tests for influence quantities of type F
Add a second paragraph, reading:
It is accepted that some small part of the effects of the influence quantities classified as Type F could be regarded as the effects produced by Type S influence quantities. If these effects are small they shall be ignored in relation to the use of this standard. If during testing larger effects of Type S are observed then the respective test shall be performed at a dose value of 10 H0 and these findings shall be reported in the type test report.
7.4 Tests for influence quantities of type S
Add a second paragraph above the note, reading:
It is accepted that some small part of the effects of the influence quantities classified as Type S could be regarded as the effects produced by Type F influence quantities. If these effects are small they should be ignored in relation to the use of this standard. If during testing larger effects of Type F or significant negative effects are observed then the respective test shall be performed at a dose value of 10 H0 and these findings shall be reported in the type test report.
8 Additivity of indicated value 8.1 Requirements
Add a note below the current text, reading:
NOTE If the algorithm used to evaluate the indicated value is either a linear combination of the signals or a linear optimization of them, then this requirement is fulfilled and no tests are required.
8.2 Method of test
Replace the text below the equation with: ∆hi,mix shall be determined for any value of HK and HL and any combination of radiation fields SK and SL. The use of computer simulation programs is permitted and recommended for this test. A prerequisite of their use is the knowledge of measured response values of each signal to all the irradiation conditions K and L and of the evaluation procedure to determine the indicated value from these signals. The simulation of the entire dosemeter to determine the response values of each signal to all the irradiation conditions is not permitted. NOTE 1 The non-linearity of the signals is treated in 9.3. Therefore, the signals shall be corrected for non-linearity for this test. When different dosemeters are used to determine Hi,K, Hi,L and Hi,K+L, in addition the effect of the different dosemeters on the signals shall be corrected.
NOTE 2 The aim of the use of simulation programs is to minimize the number of irradiations. With the use of simulation programs it is possible to determine ∆hi,mis for any combination of radiation fields SK and SL without performing additional mixed irradiations but using the evaluation algorithm of the dosemeter.
8.3 Interpretation of the results
Delete note 1.
9 Radiation performance requirements and tests 9.1 General
Add the following notes below the text: NOTE 1 The requirements for the influence quantity radiation energy and angle of radiation incidence are given with respect to the reference response R0 under reference conditions (reference radiation and 0° radiation incidence, reference dose and/or dose rate and all the other reference conditions as given in Table 2). The possible reference radiations can be found for photon radiation in Table 1 of ISO 4037-1, for beta radiation in Table 1 of ISO 6980 and for neutron radiation in Table 1 of ISO 8529-1. The most used reference radiations are given in Table 1, but especially for neutron dosemeters it can be necessary to choose other radiations as reference radiation to comply with the requirements for this influence quantity, even an energy value can be chosen as reference condition for which no physical radiation is available. In that case this (virtual) reference radiation is realized by an available reference radiation and the deviation of the response to the (virtual) reference radiation.
NOTE 2 For the reasons for the non symmetric limits for the relative response due to radiation energy and angle of radiation incidence see IEC/TR 62461.
9.3 Linearity of the response
Replace the headline with “Linearity of the dose response”. 9.3.1 General
Replace the first paragraph with:
If the methods of detection are different for photon, beta or neutron radiation or for specific energy ranges of these radiations, this requirement shall be tested separately for all types of radiation.
Delete the last sentence of the second paragraph. 9.3.3 Method of test
Replace in the first paragraph of sub-paragraph a) “appropriate reference sources” with “reference sources of appropriate activity”.
9.4 Variation of the response due to dose rate dependence of dose measurements 9.4.1 General
Replace the first paragraph with:
If the methods of detection are different for photon, beta or neutron radiation or for specific energy ranges of these radiations, then this requirement shall be tested separately for all types of radiation.
9.4.2 Requirements
Replace the second sentence of the first paragraph with “The minimum rated range of use for dose rate dependence is 0,5 µSv h–1 to 1 Sv h–1 for Hp(10) from X and gamma radiations and 5 µSv h–1 to 1 Sv h–1 for Hp(0,07) from beta, X and gamma radiations and Hp(10) from neutron radiations (see Tables 3 to 5).”
Replace the first sentence of the second paragraph with “In addition, for dosemeters to measure Hp(10) from X and gamma radiations, the variation of the relative response due to low dose rates down to natural environmental radiation shall be tested.”
Replace in the second sentence of the second paragraph “The manufacturer shall at least state” with “For that purpose the manufacturer shall state”.

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9.4.4 Method of test using natural radiation
Replace the headline with “Method of test for photon dosemeters using natural radiation”.
Replace the text of 9.4.4 with:
Place the dosemeter on the appropriate phantom for at least one week (tenv) in a normal laboratory environment and assume as a first estimate a background dose rate nattrue,H& of 2 µSv d–1, if no other information is available. Determine the instrument’s accumulated dose Hi,nat for time tenv (see also 6.9). Calculate the expected dose value from the known dose rate due to natural environmental radiation Htrue,nat = 2 µSv d–1 × tenv. If with the obtained values for Hi,nat and Htrue,nat the requirement of 9.4.5 b) is met, then no further test is necessary.
Otherwise the following refined test is necessary. Place the dosemeter on the appropriate phantom for at least one week (tenv) in an environment where the background dose rate nattrue,H& is known and “constant”. This shall be at a standard field stations where the dose rates have been measured with reference instruments which are traceable to national standards. Determine the instrument’s accumulated dose Hi,nat for time tenv (see also 6.9). Calculate the expected dose value from the known dose rate due to natural environmental radiation: Htrue,nat = envnat true,tH×&.
9.4.5 Interpretation of the results
Replace the text of 9.4.5 with:
a) The variation of the relative response due to dose rate dependence determined in 9.4.3 shall not exceed ± 0,2.
b) For photon dosemeters to measure Hp(10) from X and gamma radiations the difference between Hi,nat and Htrue,nat obtained in 9.4.4 and extrapolated for the stated maximum measuring time tmax, shall not exceed H0: 0maxenvnat true,nat i,HttHH≤×−.
NOTE This inequation can also be used to fix (new) values for H0 and tenv.
In case these requirements are met, the requirements of 9.4.2 can be considered to be met.
9.5 Variation of the response due to photon radiation energy and angle of incidence 9.5.1 Measuring quantity Hp(0,07) or &Hp(0,07) 9.5.1.1 Requirements
Add a further paragraph in between the first and second paragraphs, reading:
If the methods of detection are different for specific dose (rate) ranges, this requirement shall be tested separately for all these ranges. 9.5.1.2 Method of test
Add at the end of the first paragraph: ”, otherwise low air kerma rate series or K-fluorescence reference radiations of ISO shall be used”.

9.5.2 Measuring quantity Hp(10) or &Hp(10) 9.5.2.1 Requirements
Add a note below the last paragraph, reading NOTE The two minimum rated ranges reflect the two main workplace conditions. The minimum rated range of use from 80 keV to 1,5 MeV is for workplaces where gamma sources are used, e.g. in industry, and the minimum rated range of use from 20 keV to 150 keV is for workplaces where X-rays are used, e.g. in medical diagnostic. Both ranges can be extended until in the extreme case the rated range of use covers all energies from 10 keV to 10 MeV.
9.6 Variation of the response due to neutron radiation energy and angle of incidence 9.6.1 Measuring quantity Hp(10) or &Hp(10) 9.6.1.1 Requirements
Replace the text of 9.6.1.1 with: The relative response due to radiation energy and angle of radiation incidence for neutron radiation shall be within 0,65 to 4,0 for the energy range between the minimum energy of the rated range and 100 keV, shall be from 0,65 to 2,22 for the energy range between 100 keV and 10 MeV and shall be from 0,65 to 4,0 for the energy range between 10 MeV and the maximum energy of the rated range (see Table 5). The minimum rated range of use covers energies between 0,025 eV and 5 MeV and angles of radiation incidence between 0° and 60° (see Table 5). If the methods of detection are different for specific dose (rate) ranges, this requirement shall be tested separately for all these ranges. All indicated dose values shall be corrected for non-linear response and, if necessary, for the effect of the influence quantity dose rate on dose measurements. 9.6.1.2 Method of test
In the second paragraph, add “nearly” in between “personal dose equivalent greater than 50 % and one” and “mono energetic neutron field between 10 keV and 100 keV” and add “appropriate” between “If the rated range is extended above 15 MeV, additional” and “energies shall be used”.
Replace sub-paragraph c) with:
c) If the response for up to two mono energetic neutron fields in the energy range from 100 keV to 10 MeV is out of the limits given in 9.6.1.1, then simulated work place fields or broad sources shall be used instead. The mean energy (dose equivalent weighted) of the mono energetic and the replacement neutron fields shall be within a factor of 1/1,5 to 1,5. 9.6.1.3 Interpretation of the results
Replace the first sentence of 9.6.1.3 with:
All the relative response values due to neutron radiation energy and angle of incidence shall be within the interval from 0,65 to 4,0 for the energy range between the minimum energy of the rated range and 100 keV, shall be within the interval from 0,65 to 2,22 for the energy range between 100 keV and 10 MeV and shall be within the interval from 0,65 to 4,0 for the energy range between 10 MeV and the maximum energy of the rated range.

– 9 –
9.7 Variation of the response due to beta radiation energy and angle of incidence 9.7.1 Measuring quantity Hp(0,07) or &Hp(0,07) 9.7.1.1 Requirements
Add a new paragraph below the first paragraph, reading
If the methods of detection are different for specific dose (rate) ranges, this requirement shall be tested separately for all these ranges.
9.9 Overload characteristics 9.9.1 General
Add “or for specific energy ranges of these radiations,” between “photon, beta and neutron radiation” and “then this requirement shall be tested separately”. 9.9.3 Method of test and interpretation of results 9.9.3.3 Dose equivalent rate meters
Delete “appropriate” in the second paragraph.
9.10 Alarm 9.10.2 Response time for dose equivalent rate indication and alarm 9.10.2.1 Requirements
Replace the text of 9.10.2.1 with:
When the dosemeter is subjected to a step increase or decrease in dose equivalent rate of one order of magnitude within the effective range of the dosemeter, the readout shall indicate the new dose equivalent rate with an error of less than 20 % of the upper dose equivalent rate value within 10 s and the alarm, if set to one half of the upper dose equivalent rate value, shall respond within 2 s. These requirements shall apply for changes from background dose equivalent rates to upper case dose equivalent rate values which are greater than 1 mSv h–1 for )10(pH& from X and gamma radiation and 10 mSv h–1 for )07,0(pH& from X, gamma and beta radiation and 10 mSv h–1 for )10(pH& from neutron radiation. Alternatively, any delay of more than 2 s in the alarm responding or 10 s in the indication shall not result in the receipt of a dose in excess of 10 µSv for )10(pH& from X and gamma radiation and 100 µSv for )07,0(pH& from X, gamma and beta radiation and 500 µSv for )10(pH& from neutron radiation.
9.10.2.2 Method of test and interpretation of the results
Replace the text of 9.10.2.2 with:
For this test the dosemeter shall be placed in the irradiation facility in non-irradiating conditions and allowed to stabilize. The irradiation facility shall then rapidly be set to irradiating conditions and readings recorded continuously until the dosemeter stabilizes at the new upper dose equivalent rate. The change to 80 % of the high reading highH& shall take less than 10 s and the alarm, if set to one half of the dose equivalent rate reading, 0,5 highH&, shall respond within 2 s. Next the irradiation facility shall rapidly be set to non-irradiating conditions. The dosemeter reading shall be below 20 % of the reading highH& within 10 s and the alarm, if set to one half of the dose equivalent rate reading, 0,5 highH&, shall stop within 2 s. The dose accrued during the delay in the alarm responding shall be measured. When, in any case

where the delay is greater than 2 s, the dose is less than 10 µSv for )10(pH& from X and gamma radiation and 100 µSv for )07,0(pH& from X, gamma and beta radiation and 500 µSv for )10(pH& from neutron radiation, the requirements of 9.10.2.1 can be considered to be met. This test shall be performed for one highH& value for each order of magnitude of the effective range of the dosemeter.
10 Electrical and environmental performance requirements and tests 10.1 General
Replace the text of 10.1 with:
All influence quantities dealt with in this clause are regarded as of type F, although some of them can be partly also of type S, see 7.3.
10.2 Power supplies – Battery operation 10.2.1 General requirements
Add in the note “last” between “This” and “requirement”.
10.6 Sealing
Delete the last sentence.
11 Electromagnetic performance requirements and tests 11.1 General
Renumber the current note to “NOTE 1”.
Add a second note below, reading: NOTE 2 For special applications the electromagnetic performance requirements can be reduced, if the workplace environment assures proper operation. For example, in an reactor, where mobile phones are prohibited, the requirements of 11.4 may be excluded. In such cases, special agreements between customer and supplier are necessary together with a warning in the documentation.
13 Uncertainty
Add at the end of the first sentence of the first paragraph ”, see IEC/TR 62461".
Start the second sentence of the first paragraph “The uncertainty depends on …”.
Add at the end of the second paragraph “and IEC/TR 62461.”
14 Documentation 14.2 Certificate
Add a further dash below “maximum possible measuring time tmax (see 9.4.2)":
– indication due to zero effect and natural environmental radiation and the method to determine it (see 6.9 and 9.4.2);
Add a further dash below the whole listing:
– the usage category according to Annex ZA may be indicated.

– 11 –
Table 1 - Symbols (and abbreviated terms)
Replace the entries in the right column of the last three rows with “–“.
Table 3 - Radiation characteristics of Hp(0,07) dosemeters for X, gamma and beta radiation
Replace line 1 with: 1 Variation of the relative response due to the non-linearity of the response itself 1 mSv to 10 Sv for personal dose equivalent ±15 % a)
dose equivalent meter 9.3
Replace line 8 with: 8 Dose rate
5 µSv h–1 to 1 Sv h–1 d) ±20 % a) 9.4
Replace line 10 with: 10 Response time for dose equivalent rate indication and alarm functions )07,0(pH&U>U 10 mSv h–1
±20 % for the indication and any delay of more than 2 s in the alarm responding shall not result in the receipt of a dose in excess of 100 µSv 9.10.2
Delete line 12 and footnote e).
Table 4 - Radiation characteristics of Hp(10) dosemeters for X and gamma radiation
Replace line 1 with: 1 Variation of the response due to the non-linearity of the response itself 100 µSv to 1 Sv for personal dose equivalent ±15 % a)
dose equivalent meter 9.3
Replace line 9 with: 9 Response time for dose equivalent rate indication and alarm functions )10(pH&U>U 1 mSv h–1
±20 % for the indication and any delay of more than 2 s in the alarm responding shall not result in the receipt of a dose in excess of 10 µSv 9.10.2
Replace line 11 with: 11 Response due to zero effect and natural background radiation — Deviation of the indication during tmax from the natural background less than H0 9.4.2

Table 5 - Radiation characteristics of Hp(10) dosemeters for neutron radiation
Replace lines 1 to 4 with: 1 Variation of the response due to the non-linearity of the response itself 100 µSv to 1 Sv for personal dose equivalent ±15 % a)
dose equivalent meter 9.3 2 Statistical fluctuation, v: dose equivalent
H
< 100 µSv 100 µSv ≤ H < 5 100 µSv H ≥ 5 100 µSv 25 % (25,4 – H/(250 µSv)) % 5 % 9.3.5 3 Statistical fluctuation, v: dose equivalent rate for alarm functions H& < 1 mSv h–1 1 mSv h–1 ≤ H& < 6 mSv h–1 H&≥ 6 mSv h–1 20 % (21 – H&/(1 mSv h–1)) % 15 % 9.3.5 4 Radiation energy
and
angle of incidence 0,025 eV to 100 keV plus
100 keV to 10 MeV plus
10 MeV to 15 MeV and 0° to 60° from reference direction under consideration –35 % to +300 % b) c) –35 % to +122 % b) c) –35 % to +300 % b) 9.6.1
Replace line 6 with: 6 Dose rate
5 µSv h–1 to 1 Sv h–1 d) ±20 % a) 9.4
Replace line 8 with: 8 Response time for dose equivalent rate indication and alarm functions )10(pH&U>U 10 mSv h–1
±20 % for the indication and any delay of more than 2 s in the alarm responding shall not result in the receipt of a dose in excess of 500 µSv 9.10.2
Delete line 10 and footnote e).
Annex B (informative) Procedure to determine the variation of the relative response due to radiation energy and angle of radiation incidence
Replace “response” with “relative response” all over Annex B.
Replace the first paragraph with:
The easiest way to determine the rated range of radiation energy is to measure the (absolute) response values for all energies and angles of incidence for all radiation qualities within the anticipated rated range. Special care shall be taken at large polar angles of incidence, because the response might also depend on the azimuth angle. Then the relative response values are determined by dividing all these (absolute) response values by the value of the (absolute) response for the reference energy and 0° radiation incidence. If all relative response values are within the allowed limits (for example 0,71 – Urel and 1,67 + Urel for photon radiation) then the anticipated rated range can be stated as rated range of the dosemeter. This rated range may not be the maximum possible rated range, because even lower or higher energies may fulfil the requirements and thus larger rated ranges may be possible. In addition, especially for neutron dosemeters, a change of the reference energy may lead to a larger rated range. A better and more direct way to determine the maximum rated range, especially for photon radiation, is given in the following.
Add “for photon radiation” behind “0,71 – Urel to 1,67 + Urel” (six times).

– 13 –
Add additional Annexes ZA and ZB:
Annex ZA
(informative) Usage categories of personal dosemeters The usage categories given in Table ZA.1 can be used to categorize personal dosemeters for approval purposes. Table ZA.1 – Usage categories of personal dosemeters Optional extensions Category Symbol Minimum required range of use for energy range for dose range for dose rate range Hp(10)
Gamma radiation G 80 keV to 1,5 MeV a) 100 µSv to 10 Sv b) 0,5 µSv h–1 to 1 Sv h–1 c) m (mid): lower limit 60 keV l (low): lower limit 20 keV h (high): includes 6 MeV
f: lower limit 10 µSv
a (accident): upper limit 10 Sv/h e (environmental):
lower limit 0,05 µSv h–1 Hp(10)
X radiation X 20 keV to 150 keV a) 100 µSv to 10 Sv b) 0,5 µSv h–1 to 1 Sv h–1 c) l (low): lower limit 10 keV h (high): includes 300 keV f: lower limit 10 µSv
a (accident):
upper limit 10 Sv h–1 e (environmental):
lower limit 0,05 µSv h–1 Hp(10)
Neutron radiation N 0,025 eV to 15 MeV a) 100 µSv to 1 Sv b) 5 µSv h–1 to 1 Sv h–1 c)
f: lower limit 10 µSv a (accident):
upper limit 10 Sv h–1 e (environmental):
lower
limit 0,5 µSv h–1 Hp(0,07)
X, gamma radiation S
skin 30 keV to 250 keV a) 1 mSv to 10 Sv b) 5 µSv h–1 to 1 Sv h–1 c) l: lower limit 20 keV n: lower limit 15 keV g: lower limit 100 µSv a (accident):
upper limit 10 Sv h–1 e (environmental): lower
limit 0,5 µSv h–1 Hp(0,07)
Beta radiation B 200 keV to
800 keV (Emean) a) 1 mSv to 10 Sv b) 5 µSv h–1 to 1 Sv h–1 c) l: lower limit 60 keV (Emean) g: lower limit 100 µSv a (accident):
upper limit 10 Sv h–1 e (environmental):
lower
limit 0,5 µSv h–1 a) Minimal rated energy range b) Minimal effective range of measurement c) Minimal rated range of use for influence quantity dose rate
Example: A personal gamma neutron dosemeter for a nuclear plant may be classified as Gmh-N.

Annex ZB
(normative)
Normative references to international publications with their corresponding European publications
The following referenced documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies.
NOTE
When an international publication has been modified by common modifications, indicated by (mod), the relevant EN/HD applies.
Publication Year Title EN/HD Year
IEC 60050-151 2001 International Electrotechnical Vocabulary (IEV) -
Part 151: Electrical and magnetic devices - -
IEC 60050-393 2003 International Electrotechnology Vocabulary (IEV) -
Part 393: Nuclear instrumentation - Physical phenomena and basic concepts - -
IEC 60050-394 1995 International Electrotechnical Vocabulary (IEV) -
Chapter 394: Nuclear instrumentation: Instruments - -
IEC 60068-2-32 + A2 1975 1990 Environmental testing -
Part 2: Tests - Test Ed: Free fall
EN 60068-2-32
IEC 60086-1 2000 Primary batteries -
Part 1: General EN 60086-11) 2001
IEC 60359 2001 Electrical and electronic measurement equipment - Expression of performance EN 60359 2002
IEC 61000-4-2 A1 A2 1995 1998 2000 Electromagnetic compatibility (EMC) -
Part 4-2: Testing and measurement techniques - Electrostatic discharge immunity test EN 61000-4-2 A1 A2 1995 1998 2001
IEC 61000-4-3 2002 Electromagnetic compatibility (EMC) -
Part 4-3: Testing and measurement techniques - Radiated, radio-frequency, electromagnetic field immunity test EN 61000-4-32)
IEC 61000-4-4 A1 A2 1995 2000 2001 Electromagnetic compatibility (EMC) -
Part 4-4: Testing and measurement techniques - Electrical fast transient/burst immunity test EN 61000-4-43) A1 A2
1995 2001 2001
IEC 61000-4-5 A1 1995 2000 Electromagnetic compatibility (EMC) -
Part 4-5: Testing and measurement techniques - Surge immunity test EN 61000-4-54) A1 1995 2001
——————— 1) EN 60086-1 is superseded by EN 60086-1:2007, which is based on IEC 60086-1:2006. 2) EN 61000-4-3 is superseded by EN 61000-4-3:2006, which is based on IEC 61000-4-3:2006. 3) EN 61000-4-4 is superseded by EN 61000-4-4:2004, which is based on IEC 61000-4-4:2004. 4) EN 61000-4-5 is superseded by EN 61000-4-5:2006, which is based on IEC 61000-4-5:2005.

– 15 –
Publication Year Title EN/HD Year IEC 61000-4-6 2003 Electromagnetic compatibility (EMC) -
Part 4-6: Testing and measurement techniques - Immunity to conducted disturbances, induced by radio-frequency fields - -
IEC 61000-4-8 A1 1993 2000 Electromagnetic compatibility (EMC) -
Part 4-8: Testing and measurement techniques - Power frequency magnetic field immunity test EN 61000-4-8 A1 1993 2001
IEC 61000-4-11 2004 Electromagnetic compatibility (EMC) -
Part 4-11: Testing and measurement techniques - Voltage dips, short interruptions and voltage variations immunity tests EN 61000-4-11 2004
IEC 61000-6-2 (mod) 1999 Electromagnetic compatibility (EMC) -
Part 6-2: Generic standards - Immunity for industrial environments EN 61000-6-25)
IEC 61187 (mod) 1993 Electrical and electronic measuring equipment - Documentation EN 61187 + corr. March
1994 1995
IEC/TR 62461 2006 Radiation protection instrumentation - Determination of uncertainty in measurement - -
ISO 4037-1 1996 X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy -
Part 1: Radiation characteristics and production methods - -
ISO 4037-2 1997 X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy -
Part 2: Dosimetry for radiation protection over the energy ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV - -
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 1996 Reference beta radiations for calibrating dosemeters and dose-rate meters and for determining their response as a function of beta-radiation energy - -
ISO 8529-1 2001 Reference neutron radiations -
Part 1: Characteristics and methods of production - -
——————— 5) EN 61000-6-2 is superseded by EN 61000-6-2:2005, which is based on IEC 61000-6-2:2005.

Publication Year Title EN/HD Year ISO 8529-2 2000 Reference neutron radiations -
Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field - -
ISO 8529-3 1998 Reference neutron radiations -
Part 3: Calibration of area and personal dosimeters and determination of response as a function of energy and angle of incidence - -
ISO 12789 2000 Reference neutron radiations - Characteristics and methods of production of simulated workplace neutron fields - -
ISO 12789-2 200X6) Reference neutron radiation -
Part 2: Calibration fundamentals related to the basic quantities characterizing simulated workplace neutron fields - -
ISO/IEC Guide
1995 Guide to the expression of uncertainty in measurement (GUM) - -
ICRU report 51 1993 Quantities and units in radiation protection dosimetry - -
ICRU report 60 1999 Fundamental Quantities and Units for Ionizing Radiation - -
——————— 6) At draft stage.
NORME INTERNATIONALECEIIEC INTERNATIONAL STANDARD 61526Deuxième éditionSecond edition2005-02 Instrumentation pour la radioprotection – Mesure des équivalents de dose individuels Hp(10) et Hp(0,07) pour les rayonnements
X, gamma, neutron et bêta – Appareils de mesure à lecture directe et
moniteurs de l'équivalent de dose individuel
Radiation protection instrumentation – Measurement of personal dose equivalents Hp(10) and Hp(0,07) for X, gamma, neutron and beta radiations – Direct reading personal dose equivalent meters and monitors
Pour prix, voir catalogue en vigueur For price, see current catalogue© IEC 2005
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3, rue de Varembé, PO Box 131, CH-1211 Geneva 20, SwitzerlandTelephone: +41 22 919 02 11 Telefax: +41 22 919 03 00 E-mail: inmail@iec.ch
Web: www.iec.ch CODE PRIX PRICE CODE XA Commission Electrotechnique InternationaleInternational Electrotechnical Commission

61526Ó IEC:2005– 3 –CONTENTSFOREWORD.9INTRODUCTION.131Scope and object.152Normative references.173Terms and definitions.214Units and list of symbols.334.1Units.334.2List of symbols.335Mechanical characteristics.375.1Size.375.2Mass.375.3Case.395.4Switches.396General characteristics.396.1Personal dose equivalent meter classification.396.2Indication.396.3Dosemeter markings.396.4Retention of radioactive contamination.396.5Ranges for dose equivalent and dose equivalent rate.396.6Effective range of measurement.396.7Rated range of an influence quantity.416.8Use of more than one dosemeter.416.9Zero effect and indication due to natural environmental radiation.416.10Resettable dose or dose rate alarms.416.11Indication of malfunction.437General test procedures.437.1Nature of tests.437.2Reference conditions and standard test conditions.437.3Tests for influence quantities of type F.437.4Tests for influence quantities of type S.437.5Choice of phantom for testing.457.6Position of dosemeter for the purpose of testing.457.7Position of dosemeter during use.457.8Minimum rated range of influence quantity.457.9Low dose equivalent rates.457.10Statistical fluctuations.457.11Production of reference radiation.478Additivity of indicated value.478.1Requirements.478.2Method of test.478.3Interpretation of the results.47

61526Ó IEC:2005– 5 –9Radiation performance requirements and tests.499.1General.499.2Consideration of the uncertainty of the conventional true value.499.3Linearity of the response.499.4Variation of the response due to dose rate dependence of dosemeasurements.519.5Variation of the response due to photon radiation energy and angle ofincidence.539.6Variation of the response due to neutron radiation energy and angle ofincidence.579.7Variation of the response due to beta radiation energy and angle ofincidence.599.8Retention of dose equivalent reading.619.9Overload characteristics.639.10Alarm.639.11Model function.6710Electrical and environmental performance requirements and tests.6910.1General.6910.2Power supplies – Battery operation.6910.3Ambient temperature.7310.4Relative humidity.7510.5Atmospheric pressure.7510.6Sealing.7710.7Storage.7711Electromagnetic performance requirements and tests.7711.1General.7711.2Electrostatic discharge.7711.3Radiated electromagnetic fields.7911.4Radiated electromagnetic fields of mobile phones or wireless LAN.7911.5Conducted disturbances induced by fast transients or bursts.8111.6Conducted disturbances induced by surges.8111.7Conducted disturbances induced by radio­frequencies.8311.850 Hz/60 Hz magnetic field.8311.9Voltage dips and short interruptions.8312Mechanical performance, requirements and tests.85
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