iTeh StandardsiTeh Standards
EURUSD
Your shopping cart is empty.
SIST

SIST EN ISO 23548:2025

(Main)

Measurement of radioactivity - Alpha emitting radionuclides - Generic test method using alpha spectrometry (ISO 23548:2024)

Measurement of radioactivity - Alpha emitting radionuclides - Generic test method using alpha spectrometry (ISO 23548:2024)

This document describes a generic test method for measuring alpha emitting radionuclides, for all types of samples (soil, sediment, construction material, foodstuff, water, airborne, environmental bio-indicator, human biological samples as urine, faeces etc.) by alpha spectrometry. This method can be used for any type of environmental study or monitoring of alpha emitting radionuclides activities.
If relevant, this test method requires appropriate sample pre-treatment followed by specific chemical separation of the test portion in order to obtain a thin source proper to alpha spectrometry measurement.
This test method can be used to determine the activity, specific activity or activity concentration of a sample containing alpha emitting radionuclides such as 210Po, 226Ra, 228Th, 229Th, 230Th, 232Th, 232U,234U, 235U, 238U, 238Pu, 239+240Pu, 241Am or 243+244Cm.
This test method can be used to measure very low levels of activity, one or two orders of magnitude less than the usual natural levels of alpha emitting radionuclides. Annexes B of UNSCEAR 2000 and UNSCEAR 2008  give, respectively, typical natural activity concentrations for air, foods, drinking waters and, soils and building materials. The detection limit of the test method depends on the amount of the sample material analysed (mass or volume) after concentration, chemical yield, thickness of measurement source and counting time.
The quantity of the sample to be collected and analysed depends on the expected activity of the sample and the detection limit to achieve.

Messung der Radioaktivität - Alpha emittierende Radionuklide - Generisches Prüfverfahren mit Alphaspektrometrie (ISO 23548:2024)

Mesurage de la radioactivité - Radionucléides émetteurs alpha - Méthode d’essai générique par spectrométrie alpha (ISO 23548:2024)

Merjenje radioaktivnosti - Radionuklidi, ki oddajajo sevanje alfa - Generična preskusna metoda z uporabo alfa spektrometrije (ISO 23548:2024)

General Information

Status
Published
Public Enquiry End Date
30-Jul-2025
Publication Date
15-Oct-2025
ICS
17.240 - Radiation measurements
Technical Committee
I13 - Imaginarni 13
Current Stage
6060 - National Implementation/Publication (Adopted Project)
Start Date
09-Oct-2025
Due Date
14-Dec-2025
Completion Date
16-Oct-2025
Ref Project
EN ISO 23548:2025 - Measurement of radioactivity - Alpha emitting radionuclides - Generic test method using alpha spectrometry (ISO 23548:2024)
SIST EN ISO 23548:2025SIST EN ISO 23548:2025
PreviousNext
Standard
SIST EN ISO 23548:2025
English language
47 pages
sale 10% off
Preview
sale 10% off
Preview
e-Library read for
1 day

Standards Content (Sample)


SLOVENSKI STANDARD
01-december-2025
Merjenje radioaktivnosti - Radionuklidi, ki oddajajo sevanje alfa - Generična
preskusna metoda z uporabo alfa spektrometrije (ISO 23548:2024)
Measurement of radioactivity - Alpha emitting radionuclides - Generic test method using
alpha spectrometry (ISO 23548:2024)
Messung der Radioaktivität - Alpha emittierende Radionuklide - Generisches
Prüfverfahren mit Alphaspektrometrie (ISO 23548:2024)
Mesurage de la radioactivité - Radionucléides émetteurs alpha - Méthode d’essai
générique par spectrométrie alpha (ISO 23548:2024)
Ta slovenski standard je istoveten z: EN ISO 23548:2025
ICS:
17.240 Merjenje sevanja Radiation measurements
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EN ISO 23548
EUROPEAN STANDARD
NORME EUROPÉENNE
September 2025
EUROPÄISCHE NORM
ICS 17.240
English Version
Measurement of radioactivity - Alpha emitting
radionuclides - Generic test method using alpha
spectrometry (ISO 23548:2024)
Mesurage de la radioactivité - Radionucléides Messung der Radioaktivität - Alpha emittierende
émetteurs alpha - Méthode d'essai générique par Radionuklide - Generisches Prüfverfahren mit
spectrométrie alpha (ISO 23548:2024) Alphaspektrometrie (ISO 23548:2024)
This European Standard was approved by CEN on 22 September 2025.

CEN members are bound to comply with the CEN/CENELEC Internal Regulations which stipulate the conditions for giving this
European Standard the status of a national standard without any alteration. Up-to-date lists and bibliographical references
concerning such national standards may be obtained on application to the CEN-CENELEC Management Centre or to any CEN
member.
This European Standard exists in three official versions (English, French, German). A version in any other language made by
translation under the responsibility of a CEN member into its own language and notified to the CEN-CENELEC Management
Centre has the same status as the official versions.

CEN members are the national standards bodies of Austria, Belgium, Bulgaria, Croatia, Cyprus, Czech Republic, Denmark, Estonia,
Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway,
Poland, Portugal, Republic of North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Türkiye and
United Kingdom.
EUROPEAN COMMITTEE FOR STANDARDIZATION
COMITÉ EUROPÉEN DE NORMALISATION

EUROPÄISCHES KOMITEE FÜR NORMUNG

CEN-CENELEC Management Centre: Rue de la Science 23, B-1040 Brussels
© 2025 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 23548:2025 E
worldwide for CEN national Members.

Contents Page
European foreword . 3

European foreword
The text of ISO 23548:2024 has been prepared by Technical Committee ISO/TC 85 "Nuclear energy,
nuclear technologies, and radiological protection” of the International Organization for Standardization
(ISO) and has been taken over as EN ISO 23548:2025 by Technical Committee CEN/TC 430 “Nuclear
energy, nuclear technologies, and radiological protection” the secretariat of which is held by AFNOR.
This European Standard shall be given the status of a national standard, either by publication of an
identical text or by endorsement, at the latest by March 2026, and conflicting national standards shall
be withdrawn at the latest by March 2026.
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. CEN shall not be held responsible for identifying any or all such patent rights.
Any feedback and questions on this document should be directed to the users’ national standards body.
A complete listing of these bodies can be found on the CEN website.
According to the CEN-CENELEC Internal Regulations, the national standards organizations of the
following countries are bound to implement this European Standard: Austria, Belgium, Bulgaria,
Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland,
Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Republic of
North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Türkiye and the
United Kingdom.
Endorsement notice
The text of ISO 23548:2024 has been approved by CEN as EN ISO 23548:2025 without any modification.

International
Standard
ISO 23548
First edition
Measurement of radioactivity —
2024-09
Alpha emitting radionuclides —
Generic test method using alpha
spectrometry
Mesurage de la radioactivité — Radionucléides émetteurs alpha
— Méthode d’essai générique par spectrométrie alpha
Reference number
ISO 23548:2024(en) © ISO 2024
ISO 23548:2024(en)
© ISO 2024
All rights reserved. Unless otherwise specified, or required in the context of its implementation, no part of this publication may
be reproduced or utilized otherwise in any form or by any means, electronic or mechanical, including photocopying, or posting on
the internet or an intranet, without prior written permission. Permission can be requested from either ISO at the address below
or ISO’s member body in the country of the requester.
ISO copyright office
CP 401 • Ch. de Blandonnet 8
CH-1214 Vernier, Geneva
Phone: +41 22 749 01 11
Email: copyright@iso.org
Website: www.iso.org
Published in Switzerland
ii
ISO 23548:2024(en)
Contents Page
Foreword .v
Introduction .vi
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 2
4 Symbols and units. 3
5 Principle . 4
6 Chemical reagents and equipment . 5
6.1 General .5
6.2 Chemical reagents .5
6.2.1 Water quality .5
6.2.2 Tracer solution.5
6.3 Equipment .6
7 Sampling and samples . . 9
8 Procedure . 9
8.1 General .9
8.2 Calcination .10
8.3 Sample dissolution processes.10
8.4 Specific radiochemical separation procedures .11
8.5 Methods of deposition . 12
8.5.1 Direct deposition . 12
8.5.2 Spontaneous deposition of polonium. 12
8.5.3 Microprecipitation . 13
8.5.4 Electrodeposition . 13
8.6 Measurement .14
8.6.1 Measurement geometry .14
8.6.2 Spectrum exploitation .14
8.6.3 Energy calibration. 15
8.6.4 Efficiency calibration .16
8.6.5 Global background .17
8.6.6 Chemical yield and total efficiency .17
8.6.7 Quality control sources .18
8.7 Recommended nuclear decay data .18
9 Expression of results . 19
9.1 Calculation of activity .19
9.1.1 General .19
9.1.2 Alpha activity .19
9.1.3 Uncertainty .19
9.1.4 Decision threshold . 20
9.1.5 Detection limit . 20
9.2 Calculation of sample activity .21
9.2.1 General
...

Questions, Comments and Discussion

Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.

This May Also Interest You

SIST
SIST EN ISO 6980-2:2025(Main)
Nuclear energy - Reference beta-particle radiation - Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field (ISO 6980-2:2023)
EN ISO 6980-2:2025

This document specifies methods for the measurement of the absorbed-dose rate in a tissue-equivalent slab phantom in the ISO 6980 reference beta-particle radiation fields. The energy range of the beta-particle-emitting isotopes covered by these reference radiations is 0,22 MeV to 3,6 MeV maximum beta energy corresponding to 0,07 MeV to 1,2 MeV mean beta energy. Radiation energies outside this range are beyond the scope of this document. While measurements in a reference geometry (depth of 0,07 mm or 3 mm at perpendicular incidence in a tissue‑equivalent slab phantom) with an extrapolation chamber used as primary standard are dealt with in detail, the use of other measurement systems and measurements in other geometries are also described, although in less detail. However, as noted in ICRU 56, the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is intended for those organizations wishing to establish primary dosimetry capabilities for beta particles and serves as a guide to the performance of dosimetry with an extrapolation chamber used as primary standard for beta‑particle dosimetry in other fields. Guidance is also provided on the statement of measurement uncertainties.

  • Standard
    50 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 6980-1:2025(Main)
Nuclear energy - Reference beta-particle radiation - Part 1: Methods of production (ISO 6980-1:2023)
EN ISO 6980-1:2025

This document specifies the requirements for reference beta radiation fields produced by radioactive sources to be used for the calibration of personal and area dosemeters and dose-rate meters to be used for the determination of the quantities Hp(0,07), H'(0,07;Ω), Hp(3) and H'(3;Ω), and for the determination of their response as a function of beta particle energy and angle of incidence. The basic quantity in beta dosimetry is the absorbed-dose rate in a tissue-equivalent slab phantom. This document gives the characteristics of radionuclides that have been used to produce reference beta radiation fields, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta particle energy and the dose equivalent rate at a depth of 0,07 mm in the International Commission on Radiation Units and Measurements (ICRU) sphere. The energy range involved lies between 0,22 MeV and 3,6 MeV maximum beta energy corresponding to 0,07 MeV to 1,2 MeV mean beta energy and the dose equivalent rates are in the range from about 10 µSv·h-1 to at least 10 Sv·h-1.. In addition, for some sources, variations of the dose equivalent rate as a function of the angle of incidence are given. However, as noted in ICRU 56[5], the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is applicable to two series of reference beta radiation fields, from which the radiation necessary for determining the characteristics (calibration and energy and angular dependence of response) of an instrument can be selected.
Series 1 reference radiation fields are produced by radioactive sources used with beam-flattening filters designed to give uniform dose equivalent rates over a large area at a specified distance. The proposed sources of 106Ru/106Rh, 90Sr/90Y, 85Kr, 204Tl and 147Pm produce maximum dose equivalent rates of approximately 200 mSv·h–1.
Series 2 reference radiation fields are produced without the use of beam-flattening filters, which allows large area planar sources and a range of source-to-calibration plane distances to be used. Close to the sources, only relatively small areas of uniform dose rate are produced, but this series has the advantage of extending the energy and dose rate ranges beyond those of series 1. The series also include radiation fields using polymethylmethacrylate (PMMA) absorbers to reduce the maximum beta particle energy. The radionuclides used are those of series 1; these sources produce dose equivalent rates of up to 10 Sv·h–1.

  • Standard
    29 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 6980-3:2025(Main)
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 6980-3:2023)
EN ISO 6980-3:2025

This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the operational quantities for radiation protection purposes defined by the International Commission on Radiation Units and Measurements (ICRU). However, as noted in ICRU 56, the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is a guide for those who calibrate protection-level dosemeters and dose-rate meters with beta-reference radiation and determine their response as a function of beta-particle energy and angle of incidence. Such measurements can represent part of a type test during the course of which the effect of other influence quantities on the response is examined. This document does not cover the in-situ calibration of fixed, installed area dosemeters. The term “dosemeter” is used as a generic term denoting any dose or dose-rate meter for individual or area monitoring. In addition to the description of calibration procedures, this document includes recommendations for appropriate phantoms and the way to determine appropriate conversion coefficients. Guidance is provided on the statement of measurement uncertainties and the preparation of calibration records and certificates.

  • Standard
    27 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 19361:2025(Main)
Measurement of radioactivity - Determination of beta emitters activities -Test method using liquid scintillation counting (ISO 19361:2025)
EN ISO 19361:2025

This document applies to the determination of beta emitters activity concentration using liquid scintillation counting. The method requires the preparation of a scintillation source, which is obtained by mixing the test sample and a scintillation cocktail. The test sample can be liquid (aqueous or organic), or solid (particles or filter or planchet).
NOTE            Planchet are samples, described in 8.5, out of solid material e.g. small metal, plastic or glass pans or support material made of these materials
This document describes the conditions for measuring the activity concentration of beta emitter radionuclides by liquid scintillation counting[2].
The choice of the test method using liquid scintillation counting involves the consideration of the potential presence of other beta-, alpha- and gamma emitter radionuclides in the test sample. In this case, a specific sample treatment by separation or extraction is implemented to isolate the radionuclide of interest in order to avoid any interference with other beta-, alpha- and gamma-emitting radionuclides during the counting phase.
This document is applicable to all types of liquid samples having an activity concentration ranging from about 1 Bq·l−1 to 106 Bq·l−1. For a liquid test sample, it is possible to dilute liquid test samples in order to obtain a solution having an activity compatible with the measuring instrument. For solid samples, the activity of the prepared scintillation source shall be compatible with the measuring instrument.
The measurement range is related to the test method used: nature of test portion, preparation of the scintillator - test portion mixture, measuring assembly as well as to the presence of the co-existing activities due to interfering radionuclides.
Test portion preparations (such as distillation for 3H measurement, or benzene synthesis for 14C measurement, etc.) are outside the scope of this document and are described in specific test methods using liquid scintillation[3][[4][5][6][7][8][9][10].

  • Standard
    31 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 8529-3:2024(Main)
Neutron reference radiation fields - Part 3: Calibration of area and personal dosemeters and determination of their response as a function of neutron energy and angle of incidence (ISO 8529-3:2023, including corrected version 2023-09)
EN ISO 8529-3:2024

This document provides guidance for those who calibrate protection-level dosemeters and doserate meters for area and individual monitoring with reference neutron radiation fields. This includes the determination of the response as a function of neutron energy and angle of incidence. The operational quantities recommended in ICRU Report 51 are considered. In addition to the description of procedures, this document includes appropriate definitions and conversion coefficients and provides guidance on the statement of measurement uncertainties.

  • Standard
    18 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 20045:2024(Main)
Measurement of the radioactivity in the environment - Air: tritium - Test method using bubbler sampling (ISO 20045:2023, vključno s popravljeno različico 2023-09)
EN ISO 20045:2024

This document describes a test method to determine the activity concentration of atmospheric tritium by trapping tritium in air by bubbling through a water solution.
The formulae are given for a sampling system with four bubblers. They can also be applied to trapping systems with only one trapping module consisting of two bubblers if only tritiated water vapour (HTO) is in the atmosphere to be sampled.
This document does not cover laboratory test sample results, in becquerel per litre of trapping solution, according to ISO 9698 or ISO 13168.
The test method detection limit result is between 0,2 Bq∙m-3 and 0,5 Bq∙m-3 when the sampling duration is about one week.

  • Standard
    44 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 18589-2:2024(Main)
Measurement of radioactivity in the environment - Soil - Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples (ISO 18589-2:2022)
EN ISO 18589-2:2024

This document specifies the general requirements, based on ISO 11074 and ISO/IEC 17025, for all steps in the planning (desk study and area reconnaissance) of the sampling and the preparation of samples for testing. It includes the selection of the sampling strategy, the outline of the sampling plan, the presentation of general sampling methods and equipment, as well as the methodology of the pre-treatment of samples adapted to the measurements of the activity of radionuclides in soil including granular materials of mineral origin which contain NORM or artificial radionuclides, such as sludge, sediment, construction debris, solid waste of different type and materials from technologically enhanced naturally occurring radioactive materials (mining, coal combustion, phosphate fertilizer production etc.).

  • Standard
    38 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 20044:2024(Main)
Measurement of radioactivity in the environment - Air: aerosol particles - Test method using sampling by filter media (ISO 20044:2022)
EN ISO 20044:2024

This document provides guidance for
—   the sampling process of the aerosol particles in the air using filter media. This document takes into account the specific behaviour of aerosol particles in ambient air.
—   Two methods for sampling procedures with subsequent or simultaneous measurement:
—   the determination of the activity concentration of radionuclides bound to aerosol particles in the air knowing the activity deposited in the filter;
—   the operating use of continuous air monitoring devices used for real time measurement.
This document describes the test method to determine activity concentrations of radionuclides bound to aerosol particles after air sampling passing through a filter media designed to trap aerosol particles. The method can be used for any type of environmental study or monitoring.
This document does not cover the details of measurement test techniques (gamma spectroscopy, global alpha and beta counting, liquid scintillation, alpha spectrometry) used to determine the activity deposited in the media filter, which are either based on existing standards or internal methods developed by the laboratory in charge of those measurements. Also, this document does not cover the variability of the aerosol particle sizes as given by the composition of the dust contained in ambient air. This document does not address to sampling of radionuclides bound to aerosol particles in the effluent air of nuclear facilities [see ISO 2889:2021].

  • Standard
    54 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 18589-3:2024(Main)
Measurement of radioactivity in the environment - Soil - Part 3: Test method of gamma-emitting radionuclides using gamma-ray spectrometry (ISO 18589-3:2023)
EN ISO 18589-3:2024

This document specifies the identification and the measurement of the activity in soils of a large number of gamma-emitting radionuclides using gamma spectrometry. This non-destructive method, applicable to large-volume samples (up to about 3 l), covers the determination in a single measurement of all the γ-emitters present for which the photon energy is between 5 keV and 3 MeV.
Generic test method and fundamentals using gamma-ray spectrometry are described in ISO 20042.
This document can be applied by test laboratories performing routine radioactivity measurements as a majority of gamma-emitting radionuclides is characterized by gamma-ray emission between 40 keV and 2 MeV.
The method can be implemented using a germanium or other type of detector with a resolution better than 5 keV.
This document addresses methods and practices for determining gamma-emitting radionuclides activity present in soil, including rock from bedrock and ore, construction materials and products, pottery, etc. This includes such soils and material containing naturally occurring radioactive material (NORM) or those from technological processes involving Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) (e.g. the mining and processing of mineral sands or phosphate fertilizer production and use) as well as of sludge and sediment. This determination of gamma-emitting radionuclides activity is typically performed for the purpose of radiation protection. It is suitable for the surveillance of the environment and the inspection of a site and allows, in case of accidents, a quick evaluation of gamma activity of soil samples. This might concern soils from gardens, farmland, urban or industrial sites that can contain building materials rubble, as well as soil not affected by human activities.
When the radioactivity characterization of the unsieved material above 200 μm or 250 μm, made of petrographic nature or of anthropogenic origin such as building materials rubble, is required, this material can be crushed in order to obtain a homogeneous sample for testing as described in ISO 18589‑2.

  • Standard
    45 pages
    English language
    sale 10% off
    e-Library read for
    1 day
SIST
SIST EN ISO 19238:2023(Main)
Radiological protection - Performance criteria for service laboratories performing biological dosimetry by cytogenetics - Dicentric assay (ISO 19238:2023)
EN ISO 19238:2023

This document provides criteria for quality assurance and quality control, evaluation of the performance and the accreditation of biological dosimetry by cytogenetic service laboratories using the dicentric assay performed with manual scoring.
This document is applicable to
a)    the confidentiality of personal information, for the requestor and the service laboratory,
b)    the laboratory safety requirements,
c)    the calibration sources and calibration dose ranges useful for establishing the reference dose-response curves that contribute to the dose estimation from unstable chromosome aberration frequency and the detection limit,
d)    the scoring procedure for unstable chromosome aberrations used for biological dosimetry,
e)    the criteria for converting a measured aberration frequency into an estimate of absorbed dose,
f)     the reporting of results,
g)    the quality assurance and quality control, and
h)    informative annexes containing sample instructions for requestor (see Annex A), sample questionnaire (see Annex B), sample report (see Annex C), fitting of the low dose-response curve by the method of maximum likelihood and calculating the error of the dose estimate (see Annex D), odds ratio method for cases of suspected exposure to a low dose (see Annex E), a method for determining the decision threshold and detection limit (see Annex F) and sample data sheet for recording aberrations (see Annex G).

  • Standard
    49 pages
    English language
    sale 10% off
    e-Library read for
    1 day