SIST CEN/TR 14715:2004

SLOVENSKI STANDARD
01-september-2004
9DUQRVWVWURMHY,RQL]LUQRVHYDQMHNLJDRGGDMDMRVWURML1DYRGLOR]DXSRUDER
WHKQLþQLKVWDQGDUGRYSULREOLNRYDQMXVWURMHYYVNODGX]]DNRQRGDMQLPL]DKWHYDPL
Safety of machinery - Ionizing radiation emited by machinery - Guidance for the
application of technical standards in the design of machinery in order to comply with
legislative requirements
Sicherheit von Maschinen - Von Maschinen emittierte ionisierende Strahlung - Leitfaden
zur Anwendung vontechnischen Normen bei der Konstruktion von Maschinen um den
gesetzlichen Anforderungen zu entsprechen
Sécurité des machines - Rayonnements ionisants émis par les machines - Guide pour
l'application des normes techniques dans la conception des machines afin de satisfaire
aux exigences réglementaires
Ta slovenski standard je istoveten z: CEN/TR 14715:2004
ICS:
13.110 Varnost strojev Safety of machinery
13.280 Varstvo pred sevanjem Radiation protection
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

TECHNICAL REPORT
CEN/TR 14715
RAPPORT TECHNIQUE
TECHNISCHER BERICHT
June 2004
ICS 13.220.10
English version
Safety of machinery - Ionizing radiation emited by machinery -
Guidance for the application of technical standards in the design
of machinery in order to comply with legislative requirements
Sécurité des machines - Rayonnements ionisants émis par Sicherheit von Maschinen - Von Maschinen emittierte
les machines - Guide pour l'application des normes ionisierende Strahlung - Leitfaden zur Anwendung von
techniques dans la conception des machines afin de technischen Normen bei der Konstruktion von Maschinen
satisfaire aux exigences réglementaires um den gesetzlichen Anforderungen zu entsprechen

This Technical Report was approved by CEN on 3 November 2003. It has been drawn up by the Technical Committee CEN/TC 114.

CEN members are the national standards bodies of Austria, Belgium, Cyprus, Czech Republic, Denmark, Estonia, Finland, France,
Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Slovakia,
Slovenia, Spain, Sweden, Switzerland and United Kingdom.

EUROPEAN COMMITTEE FOR STANDARDIZATION
COMITÉ EUROPÉEN DE NORMALISATION

EUROPÄISCHES KOMITEE FÜR NORMUNG

Management Centre: rue de Stassart, 36  B-1050 Brussels
© 2004 CEN All rights of exploitation in any form and by any means reserved Ref. No. CEN/TR 14715:2004: E
worldwide for CEN national Members.

Contents
1 Scope .4
2 Relevant legislation .4
2.1 European Directives .4
2.1.1 Machinery Directive 98/37/EC (Currently under revision) .4
2.1.2 Directive 96/29/EURATOM on Basic Safety Standards for the protection of the health of
workers and the general public against the dangers arising from ionizing radiation.4
2.2 National Legislation.5
3 Standard Technical Specifications .6
4 Other Sources of Information.6
5 Methodology for compliance with Machinery Directive - Radiation.6
5.1 General.6
5.2 Full compliance with ESR .7
5.3 Alternative approach to compliance with ESR .7
5.3.1 General.7
5.3.2 Reduction of emission levels .7
5.3.3 Methods for limiting the access to irradiated area.8
5.3.4 Further actions.9
6 Measurement of Radiation Emissions.9
7 Instructions for Use .9
Annex A (informative) Examples of technical standards relating to ionizing radiation emissions from
machinery .10
A.1 Type C Standards relating to machines that may emit ionizing radiation.10
A.2 Type B Standards on shielding properties of materials against ionizing radiation .15
A.3 Type B Standards relating to measurement of ionizing radiation emissions .16
Annex B (informative) Examples of documents published by International, European and national
organisations.26
Bibliography .27
Foreword
This document CEN/TR 14715:2004 has been prepared by Technical Committee CEN/TC 114 “Safety of
machinery”, the secretariat of which is held by DIN.
Annexes A and B are informative.
According to the CEN/CENELEC Internal Regulations, the national standards organizations of the following
countries are bound to announce this Technical Report: Austria, Belgium, Cyprus, Czech Republic, Denmark,
Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta,
Netherlands, Norway, Poland, Portugal, Slovakia, Slovenia, Spain, Sweden, Switzerland and United Kingdom
Introduction
Machines may emit ionizing radiation either from incorporated radioactive sources or high voltage accelerators (e.g.
X-ray machines). Exposure of people to ionizing radiation staying close to the machinery may present a risk to
health. To control these health risks, requirements are specified in European and National legislation. The
legislation that regulates the design, manufacture and supply of machines is the European Machinery Directive,
(98/37/EC). Systems for the protection of workers against the effects of ionizing radiation are specified in a
EURATOM Directive (96/29/EURATOM). Detailed technical features are set out in international, European and
national standards.
1 Scope
The purpose of this report is to give guidance on:
a) how to comply with the relevant legislative requirements, and
b) how to take into account the technical recommendations specified in International, European and National
Standards
when machines emitting ionizing radiation are designed and built.
2 Relevant legislation
2.1 European Directives
2.1.1 Machinery Directive 98/37/EC (Currently under revision)
One of the purposes of this Directive is to provide a uniform approach to maintaining or improving the level of
safety design of machinery. The Annex 1 to the Machinery Directive lists all the essential health and safety
requirements (ESRs) relating to the design and construction of machinery. Of these, ESR 1.5.10 for 'Radiation'
states:
"Machinery must be so designed and constructed that any emission of (Proposed amendment specifies both
ionizing and non-ionizing, Revision COM (2000) 899 final 2001-01-26) radiation is limited to the extent necessary
for its operation and that the effects on exposed persons are non-existent or reduced to non-dangerous
proportions."
This document gives guidance on how to comply with ESR 1.5.10 or, if it is not possible during the design or
building stage to reduce the emission levels to non-dangerous proportions, how to proceed in order to fulfil the
Machinery Directive.
When considering ionizing radiation emissions, there can be no impediment to supply of the machines within the
European Union if the requirements of the ESR 1.5.10 [ESR 1.6.11 in proposed Amendment, Revision COM (2000)
899 final 2001-01-26] have been achieved.
2.1.2 Directive 96/29/EURATOM on Basic Safety Standards for the protection of the health of workers and
the general public against the dangers arising from ionizing radiation
The requirements for the health protection of the general public and workers against the dangers of ionizing
radiation are laid down in Council Directive 96/29/EURATOM. This Directive is based on the principles put forward
by the International Commission for Radiation Protection (ICRP) in their Publication N° 60.
EURATOM Directive contains among others requirements such as:
a) maximum permissible doses compatible with adequate safety;
b) maximum permissible levels of exposure and contamination;
c) fundamental principles governing the health surveillance of workers.
In addition to the requirements for restricting exposure and dose limitation, the Council Directive 96/29/EURATOM
also make provisions for the appointment of qualified experts, designation of areas and workers, local rules,
monitoring the exposure of employees, medical supervision, notification of work activities, record keeping, etc.
There are also requirements for the investigation of high individual exposures and incidents or accidents involving
significant contamination or releases of radioactive material.
The EURATOM Directive requires potential users of sources of ionizing radiation either to give a prior report of their
intention to the relevant national authority (see article 3 (1) of EURATOM Directive) or to obtain an authorisation
from the national competent authority (see article 4 of EURATOM Directive).
As an exception, for sources considered as safe, article 3 (2) of EURATOM Directive allows the use of radioactive
substances or electrical apparatus emitting ionizing radiation without reporting or authorisation if specified
requirements are fulfilled.
For machines this exception apply if the following conditions are fulfilled:
a) machines containing radioactive sources which do not exceed defined quantities, in terms of activity or mass
activity concentration (see Annex 1 of EURATOM Directive);
b) machines containing radioactive sources exceeding the quantities or concentration values specified in a),
provided that:
1) it is of a type approved by the national competent authority;
2) if the incorporated radioactive source is constructed in the form of a sealed source;
-1
3) it does not cause, in normal operating conditions, a dose rate exceeding 1 μSv.h at a distance of 0,1 m
from any accessible surface of the machine;
4) conditions for disposal have been specified by the national competent authority;
c) operation of machines containing electrical apparatus provided that:
1) it is of a type approved by the national competent authority;
-1
2) it does not cause, in normal operating conditions, a dose rate exceeding 1 μSv.h at a distance of 0,1 m
from any accessible surface of the apparatus.
If a machine complies with one of the requirements specified under a), b) or c) it can be considered that the
machine complies also with the ESR 1.5.10 of Machinery Directive.
2.2 National Legislation
European Directives are directed at the Member States (MS), who have to incorporate the requirements into their
national legislation. National legislation for the design, construction and supply of machines have to contain
identical requirements to those set out in the Machinery Directive. European Directives for the protection of people
(e.g. 96/29/EURATOM) specify minimum requirements which may be more restrictively transcribed into national
legislation to provide a higher level of protection. Therefore users of machines emitting ionizing radiation will not
only have to comply with the national legislation arising from European Directives but also with any increased
national requirements to protect people.
3 Standard Technical Specifications
International, European and National Standards may give useful background material for designers, manufacturers
and users of machines emitting ionizing radiation. Standards may also provide technical specifications that are
relevant:
 to the measurement of ionizing radiation emissions;
 to describe techniques or give information on the reduction of emissions from machines;
 to provide data on the shielding properties of various materials.
Examples of such standards are listed in Annex A.
4 Other Sources of Information
It is recognised that there is a large volume of technical information available in the form of technical reports,
recommendations or professional guidelines giving useful background material for designers, manufacturers and
users of machines emitting ionizing radiation.
Organisations preparing such documents are for example:
 International Commission for Radiological Protection (ICRP);
 International Atomic Energy Agency (IAEA);
 Organisation for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA);
 American Standard for Testing Material (ASTM);
 National organizations in charge of health and safety.
Some relevant documents published by these organisations are given in Annex B.
5 Methodology for compliance with Machinery Directive - Radiation
5.1 General
Two types of approaches are possible to comply with Machinery Directive requirements:
 a full compliance with all the ESR 1.5.10;
 If not possible, the machinery must be designed and constructed with the purpose of approaching those
objectives (e.g. by using of additional shielding).
NOTE If compliance with ESR 1.5.10 cannot be met, in all EURATOM Directive requires additional protection measures.
These measures, which purposes are to reduce the exposure of people during operation by management or segregation, may
include:
- prohibition of non-essential access to the irradiated areas;
- remote controlled and automatic processes;
- installation of additional shielding by the user at work places;
- use of personal protective equipment;
- limiting time of exposure;
- extending the distances between the machine and the operators.
5.2 Full compliance with ESR
To achieve the requirement of the ESR, the design of a machine must restrict emissions to a level that is necessary
for the function and that the effects on exposed persons are non-existent or reduced to non-dangerous proportions.
These objectives can be met when a machine complies with one of the requirements specified under a), b) or c) of
2.1.2.
NOTE Machines that comply with the conditions specified in Article 3 of the EURATOM Directive are deemed to comply
with ESR 1.5.10.
Using such type-approved machines may provide advantages to the user:
a) the users will not be required to report to the national authorities their intention to use the machine;
b) type approval requires that the radioactive substances are in the form of sealed sources, thereby reducing the
possibility of releasing contamination;
c) machines that are type approved may be used with less restrictive controls in the workplace because they
present an inherently lower risk to workers and the environment.
To fulfil ESR 1.5.10 manufacturers may need to incorporate features in their products that reduce the emissions
from them. Where a technical specification exists for the design of that type or class of products to reduce
emissions, it should be used.
5.3 Alternative approach to compliance with ESR
5.3.1 General
If the requirements of 5.2 cannot be met, the following measures can be applied:
 reduction of emission levels by selection of suitable radiation source (radioactive source or electrical
accelerator) or by adding shielding around the process area;
 limiting the access to irradiated area by using either additional guards, mechanical shutters, or other means
intended to restrict the exposure of people.
5.3.2 Reduction of emission levels
5.3.2.1 Selection of radiation sources
The selection of radiation sources will need to consider the materials to be processed and the intended lifetime of
the machine. Balancing the following factors will be the decision of the designer, but the overriding objective is to
reduce the emissions to as low as possible while permitting the machine to function as intended.
Factors affecting the choice of radioactive sources will be:
 radionuclide half life;
 emission energy and types (alpha, beta, gamma, neutron);
 activity;
 source design (sealed, according to ISO 2919, see A.1, or unsealed);
 beam geometry (multidirectional or unidirectional);
 safe working life;
 shielding property (effectiveness, weight, volume).
Factors to be considered when selecting operational settings for electrical accelerators:
 accelerating voltage;
 beam current;
 beam geometry;
 target material;
 shielding property (effectiveness, weight, volume).
5.3.2.2 Shielding
The inclusion of shielding in the machine housing will remove or reduce radiation emissions at accessible points
around the machine. Design of the shielding has to take account of the materials selected and the construction.
Factors to be taken into account when selecting shielding:
 type of radiation;
 attenuation ability;
 radiation energy;
 secondary emissions;
 physical strength, durability, flammability, resistance to radiation damage;
 chemical form and toxicity;
 weight, volume of material.
Examples of standards providing detailed technical information about shielding properties of different materials are
given in A.2.
5.3.2.3 Special considerations regarding joints or openings
Design features such as joints or openings and their covers need special attention. If service penetrations through
the shielding materials cannot be avoided, special design requirements to control radiation leakage are to be
applied (e.g. zigzag channels, additional overlap shielding, etc.).
Other aspects to be considered include interlocking of movable shields, prevention of leaks and uncontrolled
release of radiation, use of enclosed material handling devices, process control systems,
5.3.2.4 Balancing
Source selection and shielding design will need to be balanced when making decisions.
5.3.3 Methods for limiting the access to irradiated area
To restrict exposure of people, the access to the irradiated area shall be limited. In respect to this objective, the
following requirements shall be fulfilled:
 wherever possible, the irradiated area shall be totally enclosed;
 if there is a need for access to the radiation field or beam, then access points should be included in the design.
The construction of access points shall not create leakage of radiation above the emission levels specified in
the design targets;
 if the process area is not an enclosed volume, barriers, trip devices or guards should be installed to prevent
access to this area or to provide additional radiation attenuation. If these guards are only to prevent human
access, openings shall be forbidden or their surfaces reduced as far as possible. Interlock system are
recommended.
5.3.4 Further actions
The appliance of the previous additional protective measures shall lead to the following conclusion:
-1
 the remaining emission levels do not exceed 1 μSv.h at a distance of 0,1 m from any accessible surface. In
this case, instructions of use shall contain guidance for complying with additional requirements specified by
EURATOM Directive (e.g. reporting, authorisation, source disposal);
-1
 the remaining emission levels exceed 1 μSv.h at a distance of 0,1 m from an accessible surface. In this case,
instruction of use shall contain, in addition, provisions for limiting the exposure of people during operation (see
clause 5.3.3.
6 Measurement of Radiation Emissions
Measurement of radiation emission shall be done in order to confirm adequacy of design and compliance with the
requirements listed in 5. Measurement shall be made at accessible points around the machine. Specific techniques
for measuring radiation emissions are given in standards listed in A.3.
7 Instructions for Use
Manufacturers must provide sufficient information to enable the machine to be adjusted, operated, serviced and
maintained without risks to people from the radiation emissions. Where additional barriers to prevent close
approach are needed, criteria for deciding on their selection and location must be included in the instruction
manual.
Designers need to take into account the need for sealed sources to be tested for leakage according to
standardised methods (see A.1 ISO 9978) at regular intervals. If direct testing of the source is not possible,
designers should specify an alternative technique. Information for leakage testing has to be included in the
instruction for use.
If additional protective measures for limiting the exposure of people during operation are needed, according to
EURATOM Directive (see NOTE under 5.1), these protective measures shall be specify in the instructions for use.
Annex A
(informative)
Examples of technical standards relating to ionizing radiation emissions
from machinery
A.1 Type C Standards relating to machines that may emit ionizing radiation
Number Date Title – Content
ISO 361 1975 Basic ionizing radiation symbol
Content: This standard specifies the symbol to be used to signify the potential presence of
ionizing radiation.
IEC 60777 1983 Terminology, quantities and units concerning ionizing radiation
Content: This standard defines terms, quantities and units used in radiation protection field.
ISO 921 1997 Nuclear energy – Vocabulary
Content: This standard defines terms used in nuclear energy domain.
ISO 2437 1972 Recommended practice for the X-ray inspection of fusion welded butt joints for aluminium
and its alloys and magnesium and its alloys 5 to 50 mm thick
Content: This standard provides general guidance on the techniques of weld radiography.
ISO 2855 1976 Radioactive materials – Packagings – Test for contents leakage and radiation leakage
Content: This standard specifies methods for contents leakage and radiation leakage tests
of prototypes of packages for the transport of radioactive materials. This standard may also
be of guidance to regulating authorities.
ISO 2919 1999 Radiation protection – Sealed radioactive sources – General requirements and
classification
Content: This standard establishes a system of classification of radioactive sources based
on testing performances and specifies general requirements, performances, production
tests, marking and certification. It provides a set of tests by which the manufacturer can
evaluate the safety of his product and by which the user can select types which are suitable
for the required application, especially where protection against release of radioactive
material is needed.
This standard may also be of guidance to regulating authorities.
ISO 12807 1996 Safe transport of radioactive materials – Leakage testing on packages
Content: This standard describes a method for relating permissible activity release rates of
the radioactivity content carried within a containment system equivalent gas leakage rates
under specified test conditions. It provides detailed guidance on the complex relationships
between an equivalent gas leakage test and a permissible activity release rate. This
standard may also be of guidance to regulating authorities.
ISO 9978 1992 Radiation protection – Sealed radioactive sources – Leakage test methods
Content: This standard specifies the different leakage test methods for sealed radioactive
source. It applies to control quality controls, production controls as well as to periodic
inspections for sealed radioactive sources. This standard may also be of guidance to
regulating authorities.
ISO/TR 4826 1979 Sealed radioactive sources – Leak test methods
Content: This technical report detailed the tests defined in ISO 2919.
ISO 3925 1978 Unsealed radioactive substances – Identification and certification
Content: This standard establishes the requirements for the identification and certification
of unsealed radioactive sources issued commercially by suppliers and which are intended
for further handling on treatment either physical or chemical. This standard may also be of
guidance to regulating authorities.
Number Date Title – Content
ISO 3999-1 2000 Radiation Protection – Apparatus for industrial gamma radiography – Part 1: Specifications
for performances, design and tests
Content: This standard specifies the performance, design and test requirements for
gamma radiography with portable, mobile and fixed exposure containers of the various
categories of apparatus. It applies to apparatus designed to allow the controlled used of
gamma radiation emitted by a sealed radioactive source for industrial radiography purposes
in order that persons will be safeguarded when the apparatus is used in conformity with the
regulations in force regarding radiation protection.
This standard may also be of guidance to regulating authorities.
ANSI N 432 1980 Radiological safety for the design and construction of apparatus for gamma radiography
Content: This standard specifies the design and construction requirements for apparatus
designed to allow the controlled used of gamma radiation emitted by a sealed radioactive
source for industrial radiography.
This standard may also be of guidance to regulating authorities.
ISO 7205 1986 Radionuclide gauges – Gauges designed for permanent installation
Content: This standard establishes the main characteristics for radionuclide gauges
(classification of gauges and shielding devices – technical construction and performance
requirements – control and test methods – indication to be mention).
ANSI N 538 1979 Classification of industrial ionizing radiation gauging devices
Content: This standard establishes a system of classification of industrial radiation gauging
devices.
ANSI N 439 1991 Gamma radiography – Specifications for design and testing of apparatus
Content: This standard specifies the design and test requirements for apparatus designed
to allow the controlled used of gamma radiation emitted by a sealed radioactive source for
industrial radiography.
This standard may also be of guidance to regulating authorities.
ISO 5576 1997 Non-destructive testing – Industrial X-ray and gamma-ray radiology – Vocabulary
Content: This standard defines terms used in industrial radiographic testing.
ISO 5579 1998 Non-destructive testing – Radiographic examination of metallic materials by X- and
gamma-rays – Basic rules
Content: This standard specifies the basic rules for industrial X-and gamma radiography
for flaw detection purposes, using film techniques, applicable to metallic products and
materials.
ISO 5580 1985 Non-destructive testing – Industrial radiographic illuminators – Minimum requirements
Content: This standard specifies the minimum requirements for industrial non-destructive
testing apparatuses used for viewing radiographs.
ISO 8194 1987 Radiation protection – Clothing for protection against radioactive contamination – Design,
selection, testing and use
Content: This standard gives the characteristics of clothing protecting the wearer against
radioactive contamination brought about by contact with liquid or solids substances or by
atmospheric pollutants, such as solid particles, mist, gases or vapours. It includes guidance
and recommendations for choosing protective clothing (ventilated types as well as and non
ventilated types) and test methods for measuring the leak-tightness and air supply
provisions for ventilated-pressurised protective clothing.
This standard may also be of guidance to regulating authorities.
Number Date Title – Content
ISO 8690 1988 Decontamination of radioactively contaminated surfaces – Method for testing and
assessing the ease of decontamination
Content: This standard aims to define objective conditions for testing the ease of deconta-
mination of surfaces. It applies to the testing of surfaces which may become contaminated
by radioactive materials (with any radio-nuclide in aqueous solution). The test method is
designed to obtain data allowing the comparison of the ease of decontamination of different
surface materials.
ISO 3497 2000 Metallic coatings – Measurements of coating thickness – X-ray spectrometric methods
Content: This standard specifies methods for measuring the thickness of metallic coatings
by the use of X-rays spectrometric methods.
ISO 3543 2000 Metallic and non-metallic coatings – Measurement of thickness – Beta backscattering
method
Content: This standard specifies methods for the non-destructive measurement of coating
thickness using beta scattering gauges. It applies to both metallic and non-metallic coatings
on both metallic and non-metallic substrates.
ISO 3157 1991 Radioluminescence for time measurement instruments – Specifications
Content: This standard specifies requirements for the optical, mechanical and radioactive
characteristics of the radioluminescence deposits fixed on time measurements instruments,
together with the tests methods relating to them.
ISO 1709 1995 Nuclear energy – Fissile materials – Principles of critically safety in storing, handling and
processing
Content: This standard specifies the basic principles and limitations which govern
operations with fissile materials. It discusses general criticality safety criteria for equipment
design and for the development of operating controls, while providing guidance for the
assessment of procedures, equipment and operations. Transport of fissile material is not
within its scope. This standard may also be of guidance to regulating authorities.
ISO 1106-1 1984 Recommended practice for radiographic examination of fusion welded joints – Part 1:
Fusion welded butt joints in steel plates up to 50 mm thick
ISO 1106-2 1985 Recommended practice for radiographic examination of fusion welded joints – Part 2:
Fusion welded butt joints in steel plates thicker than 50 mm and up to and including 200
mm in thickness
ISO 1106-3 1984 Recommended practice for radiographic examination of fusion welded joints – Part 3:
Fusion welded circumferential joints in steel pipes of up to 50 mm wall thickness
Content: The objective of these serial standards is to specify general techniques of weld
radiography, based on acceptable practice and fundamental theory of the subject. They do
not lay down radiographic criteria of acceptance for the joints, but are concerned with the
radiographic techniques to be used.
ISO 12789 2000 Reference neutron radiations – Characteristics and methods of production of simulated
workplace neutron fields
Content: This standard gives guidance for producing and characterizing simulated
workplace neutron fields that are to be used for calibrating neutron-measuring devices for
radiation protection purposes. Neutron energies ranges from thermal neutron to several
hundred GeV.
ISO 14146 2000 Radiation protection – Criteria and performance limits for the periodic evaluation of
processors of personal dosemeters for X and gamma radiation
Content: This standard specifies the criteria and the test procedures to be used for the
periodic verification of the performance of personal-dosemeter processors (for X and g of
10 keV to 9 MeV). It covers all type of dosemeters needing laboratory processing (e.g. pho-
tographic-film, thermoluminescent) and involving continuous or periodic measurement.
Number Date Title – Content
IEC 60405 1972 Nuclear instruments – Constructional requirements to afford personal protection against
ionizing radiation
Content: This standard contains recommendations applicable to electrical measuring
instruments incorporating a radioactive sealed or non-dispersible source for self-calibrating
or for measurement, but excepting instruments used for the control of nuclear reactors or
for medical diagnostic or therapeutic purposes.
IEC 60476 1993 Nuclear instrumentation – Electrical measuring systems and instruments utilizing ionizing
radiation sources – General aspects
Content: This standard applies to electrical measuring systems and instruments utilizing
radioactive sources and provides a basis for the development of individual new standards
concerning the performance and constructional characteristics of such apparatuses.
IEC 61560 1998 Radiation protection instrumentation – Apparatus for non-destructive radiation tests of fur
and other cloth samples
Content: This standard applies to portable instruments used for measuring the specific
activity of beta-emitting radionuclides on fur and other cloth sample. It specifies
performance characteristics, test procedures and documentation requirements.
IEC 61344 1996 Radiation protection instrumentation – Monitoring equipment – Personal warning devices
for X and gamma radiations
Content: This standard applies to audible or audible and visual warning portable devices,
used to give an indication of personal dose equivalent rate, from X and gamma radiations
(from 60 keV to 1,5 MeV). It specifies general as well as environmental characteristics, test
procedures and electrical and mechanical safety requirements.
IEC 61336 1996 Nuclear instrumentation – Thickness measurement systems utilizing ionizing radiation –
Definitions and test methods
Content: This standard relates to definitions, test methods, and procedures for ionizing
radiation measurements systems designed for continuous or periodic measurements and
checks thickness of materials produced in industrial processes (e.g. sheets, coatings,
laminates, tubes or rods).
EN 12543-1 1999 Non-destructive testing – Characteristics of focal spots in industrial X-ray systems for use in
non-destructive testing – Part 1: Scanning method
EN 12543-2 1999 Non-destructive testing – Characteristics of focal spots in industrial X-ray systems for use in
non-destructive testing – Part 2: Pinhole camera radiographic method
EN 12543-3 1999 Non-destructive testing – Characteristics of focal spots in industrial X-ray systems for use in
non-destructive testing – Part 3: Slit camera radiographic method
EN 12543-4 1999 Non-destructive testing – Characteristics of focal spots in industrial X-ray systems for use in
non-destructive testing – Part 4: Edge method
EN 12543-5 1999 Non-destructive testing – Characteristics of focal spots in industrial X-ray systems for use in
non-destructive testing – Part 5: Measurement of the effective focal spot size of mini and
micro focus X-ray tubes
Content: This series of standards specifies the method of determination of the dimension
of the focal spots of industrial X-ray tubes, according to the high voltage level, for the
different applications mentioned.
EN 12544-1 1999 Non-destructive testing – Measurement and evaluation of the X-ray tube voltage – Part 1:
Voltage divider method
EN 12544-2 2000 Non-destructive testing – Measurement and evaluation of the X-ray tube voltage – Part 2:
Constancy check by the thick filter method
EN 12544-3 1999 Non-destructive testing – Measurement and evaluation of the X-ray tube voltage – Part 3:
Spectrometric method
Content: This series of standards specifies the method of determination of the high voltage
levels set on the X-ray tubes, for the different type of applications mentioned here above.
Number Date Title – Content
IEC 61336 1996 Nuclear instrumentation – Thickness measurement systems utilizing ionizing radiation-
Definitions and test methods
Content: This standard relates to definitions, test methods, and procedures for ionizing
radiation measurements systems designed for continuous or periodic measurements and
checks thickness of materials produced in industrial processes (e.g. metallic sheets,
coatings, laminates, tubes or rods, plastics material, wood, etc.).
EN 12679 1999 Non-destructive testing – Determination of the size of industrial radiographic sources (ISO
11553: 1996 modified)
Content: This standard defines, by use of a X-ray radiotherapy technique, the methodology
for determining the dimension of a gamma emission sources obtained with following
192 169 75 60
radionuclides I, Y, Se and Co.
HD 435 S1 1983 Density meters utilizing ionizing radiation – Definitions and test methods
Content: This standard establishes the main characteristics for radionuclide density meter
(classification of density meters and shielding devices – technical construction and
performance requirements – control and test methods – indication to be mention).
HD 468 S1 1987 Ionizing radiation measurement monitoring equipment with analogue or digital signal
processing for thickness measurement
Content: This standard applies to monitors using radioactive emission sources for
thickness measurements. It specifies performance requirements, test procedure and safety
features.
IEC 60692 1999 Nuclear instrumentation – Density gauges utilizing ionizing radiation – Definitions and test
methods
Content: This standard relates to definitions, test methods and procedures for density
gages utilising ionizing radiation, designed to measures the density of liquids, gas vapours,
slurries, or fluidised solids.
A.2 Type B Standards on shielding properties of materials against ionizing radiation
Number Date Title – Content
ISO 7212 1986 Enclosures for protection against ionizing radiation – Lead shielding units for 50 mm and
100 mm thick walls
Content: This standard specifies the characteristics of the standardised lead units used in
the construction of shielded enclosures to ensure the protection against ionizing radiation.
ISO 9404-1 1991 Enclosures for protection against ionizing radiation – Lead shielding units for 150 mm, 200
mm and 250 mm thick walls – Part 1: Chevron units of 150 and 200 mm thickness
ISO 9404-2 1993 Enclosures for protection against ionizing radiation – Lead shielding units for 150 mm, 200
mm and 250 mm thick walls – Part 2: Circular units of 150, 200 and 250 mm thickness
Content: Both standards specifies the characteristics of the corresponding standardised
lead units used in the construction of shielded enclosures to ensure the protection against
ionizing radiation.
ISO 14152 2002 Neutron radiation protection shielding – Design principles and considerations for the choice
of appropriate materials
Content: This standard presents the general methodology governing the design of neutron
radiation protection and the choice of neutron shielding materials. Especially in a specific
Annex it summarises the different characteristics of the most common neutron materials
existing over the world.
BSI 4094-1 Recommendation for data on shielding from ionizing radiation – Part 1: Shielding from
gamma radiation
Content: This standard provides data for shielding calculation (against gamma radiation).
BSI 4094-2 1971 Recommendation for data on shielding from ionizing Radiation – Part 2: Shielding from X-
radiation
Content: This standard provides data for shielding calculation (against X-rays).
IEC 60544-1 1994 Guide for determining the effects of ionizing radiation on isolating materials – Part 1:
Radiation interaction and dosimetry
IEC 60544-2 1994 Guide for determining the effects of ionizing radiation on isolating materials – Part 2:
Procedure or irradiation and test
IEC 60544-3 1994 Guide for determining the effects of ionizing radiation on isolating materials – Part 3: Test
methods for determining permanent effects
IEC 60544-4 1994 Guide for determining the effects of ionizing radiation on isolating materials – Part 4:
Classification system for services in radiation environment.
Content: This set of standards provides general information on effects of ionizing radiation
on isolating materials. It constitutes a guide for the selection of appropriate materials
according to the level of potential radiation exposure.
EN 60544-1 1994 Electrical insulating materials – Determination of the effects of ionizing radiation – Part 1:
Radiation interaction and dosimetry (IEC 60522: 1999)
Content: This standard provides general information on effects of ionizing radiation on
isolating materials. It constitutes a guide for the selection of appropriate materials according
to the level of potential radiation exposure.
A.3 Type B Standards relating to measurement of ionizing radiation emissions
Number Date Title – Content
IEC 60325 1981 Alpha, beta and alpha-beta contamination meters and monitors
Content: The specifications of this standard apply to alpha, beta and alpha-beta
contamination meters and monitors. It specifies the corresponding performance
requirements, test procedures, radiation characteristics, electrical, mechanical, safety and
environmental characteristics.
IEC 60333 1993 Nuclear instrumentation – Semiconductor charged-particle detectors – Test procedure
Content: This standard applies to semiconductor charged particle detectors use for
radiation emission measurements. It specifies test procedures to be applied to demonstrate
compliance with performance requirements.
IEC 60482 1975 Dimensions of electronic instrument modules (for nuclear electronic instrument)
Content: This standard specifies construction requirements and standard dimension for
electronic instrument modules.
IEC 60532 1992 Radiation protection instrumentation – Installed dose ratemeters, warning assemblies and
monitors – X and gamma radiation of energy between 50 keV and 7 MeV.
Content: This standard applies to installed dose ratemeters, warning assemblies and
monitors intended to measure exposure quantities (e.g. air kerma, ambient dose
equivalent) due to X and gamma radiations of energy between 50 keV and 7 MeV.
It lays down the corresponding performance requirements, test procedures, radiation
characteristics, electrical, mechanical, safety and environmental characteristics.
IEC 60579 1977 Radioactive aerosol contamination meters and monitors
Content: The specifications of this standard applies to radioactive aerosol contamination
meters and aerosol contamination monitors used in accordance with ISO 2889 (which gives
the general princip
...