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. __________

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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”.

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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 tra
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