Fume cupboards - Part 8: Fume cupboards for work with radioactive materials

This document specifies fume cupboards for work with unsealed radioactive materials with specific requirements regarding radiation protection and it does not apply to glove boxes or hot cells not even to α emitting radioisotopes.
The purpose of this document is to set out rules for the design and testing of fume cupboards for work with unsealed radioactive materials, in order to provide guidelines for the planner, installer, operator, assessor and the authorities.
NOTE   If, when handling unsealed radioactive substances, radiopharmaceuticals are produced for use on humans, the fume cupboards covered by this document are not sufficient.
Before using radioactive materials, a safety assessment needs to be performed. To find the maximum activity allowed for every activity with radioactive material it is necessary to take into account the three principles of radiological protection, namely justification, optimization, and the application of dose limits, clarifying how they apply to radiation sources delivering exposure and to individuals receiving exposure. Shield and abatement system required are also evaluated.

Abzüge - Teil 8: Abzüge für Arbeiten mit radioaktiven Substanzen

Dieses Dokument legt Abzüge für das Arbeiten mit offenen radioaktiven Materialien mit spezifischen Anforderungen im Hinblick auf den Strahlenschutz fest, es gilt nicht für Handschuhkästen oder heiße Zellen, auch nicht für Alphastrahler.
Zweck dieses Dokuments ist es, Regeln für die Auslegung und das Prüfen von Abzügen für das Arbeiten mit offenen radioaktiven Stoffen festzulegen, um als Leitfaden für Planer, Installateure, Benutzer, Prüfer und Behörden zu dienen.
ANMERKUNG   Wenn beim Umgang mit offenen radioaktiven Materialien Radiopharmaka zur Anwendung am Menschen hergestellt werden, sind die von diesem Dokument abgedeckten Abzüge nicht ausreichend.
Vor der Verwendung von radioaktiven Materialien ist eine Sicherheitsbewertung durchzuführen. Um den größten zulässigen Umfang für jede Tätigkeit mit radioaktiven Materialien zu bestimmen, müssen die drei Grundprinzipien des Strahlenschutzes berücksichtigt werden, nämlich Notwendigkeit, Optimierung und Einhaltung der Dosisgrenzwerte, und es muss dargelegt werden, wie diese auf Strahlenquellen und die der Strahlung ausgesetzten Personen angewendet werden. Das erforderliche Abschirmungs  und Abluft-reinigungssystem wird ebenfalls evaluiert.

Sorbonnes - Partie 8 : Sorbonnes pour matières radioactives

No Scope available

Digestoriji - 8. del: Digestoriji za delo z radioaktivnimi snovmi

Ta dokument opredeljuje digestorije za delo z nezatesnjenimi radioaktivnimi snovmi, vključno s posebnimi zahtevami glede zaščite pred sevanjem, ter se ne uporablja za komore z rokavicami, vroče celice ali radioaktivne izotope, ki oddajajo sevanje α.
Namen tega dokumenta je določiti pravila za načrtovanje in preskušanje digestorijev za delo z nezatesnjenimi radioaktivnimi snovmi, da se zagotovijo smernice za načrtovalce, monterje, upravljavce, ocenjevalce in pristojne organe.
OPOMBA:   Digestoriji, obravnavani v tem dokumentu, ne zadoščajo, kadar se pri ravnanju z nezatesnjenimi radioaktivnimi snovmi proizvajajo radiofarmacevtski proizvodi za uporabo pri ljudeh.
Pred uporabo radioaktivnih snovi je treba opraviti oceno varnosti. Da bi za vsako aktivnost radioaktivne snovi ugotovili največjo dovoljeno aktivnost, je treba upoštevati tri načela za radiološko zaščito, in sicer utemeljitev, optimizacijo ter uporabo mejnih doz, pri čemer je treba pojasniti, kako veljajo za vire sevanja, ki povzročajo izpostavljenost, ter posameznike, ki so izpostavljeni. Ovrednotena sta tudi ščit in sistem za zmanjšanje emisij.

General Information

Status
Published
Public Enquiry End Date
30-Nov-2020
Publication Date
17-Jul-2022
Technical Committee
Current Stage
6060 - National Implementation/Publication (Adopted Project)
Start Date
13-Jul-2022
Due Date
17-Sep-2022
Completion Date
18-Jul-2022

Buy Standard

Standard
EN 14175-8:2022
English language
18 pages
sale 10% off
Preview
sale 10% off
Preview
e-Library read for
1 day
Draft
prEN 14175-8:2020
English language
15 pages
sale 10% off
Preview
sale 10% off
Preview
e-Library read for
1 day

Standards Content (Sample)

SLOVENSKI STANDARD
SIST EN 14175-8:2022
01-september-2022
Digestoriji - 8. del: Digestoriji za delo z radioaktivnimi snovmi
Fume cupboards - Part 8: Fume cupboards for work with radioactive materials
Abzüge - Teil 8: Abzüge für Arbeiten mit radioaktiven Substanzen
Sorbonnes - Partie 8 : Sorbonnes pour matières radioactives
Ta slovenski standard je istoveten z: EN 14175-8:2022
ICS:
13.280 Varstvo pred sevanjem Radiation protection
71.040.10 Kemijski laboratoriji. Chemical laboratories.
Laboratorijska oprema Laboratory equipment
SIST EN 14175-8:2022 en,fr,de
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

---------------------- Page: 1 ----------------------
SIST EN 14175-8:2022

---------------------- Page: 2 ----------------------
SIST EN 14175-8:2022


EN 14175-8
EUROPEAN STANDARD

NORME EUROPÉENNE

July 2022
EUROPÄISCHE NORM
ICS 13.280; 71.040.10
English Version

Fume cupboards - Part 8: Fume cupboards for work with
radioactive materials
Sorbonnes - Partie 8 : Sorbonnes pour matières Abzüge - Teil 8: Abzüge für Arbeiten mit radioaktiven
radioactives Substanzen
This European Standard was approved by CEN on 29 May 2022.

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, Turkey 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
© 2022 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN 14175-8:2022 E
worldwide for CEN national Members.

---------------------- Page: 3 ----------------------
SIST EN 14175-8:2022
EN 14175-8:2022 (E)
Contents Page

European foreword . 3
Introduction . 4
1 Scope . 5
2 Normative references . 5
3 Terms and definitions . 5
4 Dimensions. 7
5 Basic safety and performance objectives . 7
6 Materials . 8
6.1 General requirements . 8
6.2 Protective barrier . 8
6.3 Sash . 9
7 Safety requirements . 9
7.1 General requirements . 9
7.2 Construction . 9
7.2.1 General. 9
7.2.2 Workspace . 9
7.2.3 Work surface . 10
7.2.4 Base . 11
7.2.5 Side walls . 11
7.2.6 Protective barrier . 12
7.2.7 Sash . 12
7.2.8 Abatement system . 12
8 Test methods . 12
8.1 Type testing and onsite testing . 12
8.2 Exhaust/extract air abatement system . 14
8.3 Variable air volume control . 14
9 Type test performance requirements . 14
10 Services . 14
10.1 General. 14
10.2 Drainage . 15
10.3 Liquids/water/cooling water . 15
10.4 Electric sockets . 15
11 User manual . 15
12 Marking and labelling . 15
13 Declaration of conformity . 16
Bibliography . 17


2

---------------------- Page: 4 ----------------------
SIST EN 14175-8:2022
EN 14175-8:2022 (E)
European foreword
This document (EN 14175-8:2022) has been prepared by Technical Committee CEN/TC 332 “Laboratory
equipment”, the secretariat of which is held by DIN.
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 January 2023, and conflicting national standards shall
be withdrawn at the latest by January 2023.
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 organisations 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, Turkey and the United
Kingdom.
3

---------------------- Page: 5 ----------------------
SIST EN 14175-8:2022
EN 14175-8:2022 (E)
Introduction
Before using radioactive materials, a safety (risk) assessment is performed with reference to legislation
and advice from radiation protection experts.
The maximum amount of activity allowed for every activity with radioactive material is evaluated in
accordance to the three principles of radiological protection, namely justification, optimization, and the
application of dose limits, clarifying how they apply to radiation sources delivering exposure and to
individuals receiving exposure. Shielding or abatement system when appropriate are also evaluated.
There are three kinds of dose in radiological protection. Absorbed dose is a measurable, physical
quantity, while equivalent dose and effective dose are specifically for radiological protection purposes.
Dose is used in this document as defined in IAEA Glossary 2018.
Attention is drawn to the publication IAEA SAFETY STANDARDS SERIES, Radiation Protection and Safety
of Radiation Sources: International Basic Safety Standards General Safety Requirements Part 3 (No. GSR
Part 3).
4

---------------------- Page: 6 ----------------------
SIST EN 14175-8:2022
EN 14175-8:2022 (E)
1 Scope
This document specifies the characteristics of fume cupboards, as defined in EN 14175-1, for work with
unsealed radioactive materials with specific requirements regarding radiation protection. It does not
apply to fume cupboards, glove boxes or hot cells (shielded radiation containment cells which can
incorporate fume extraction).
The purpose of this document is to set out rules for the design and testing of fume cupboards for work
with unsealed radioactive materials, in order to provide guidelines for the manufacturer, planner,
installer, operator, assessor and the authorities.
This document only covers bench type fume cupboards.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content
constitutes requirements 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.
EN 13150, Workbenches for laboratories in educational institutions - Dimensions, safety and durability
requirements and test methods
EN 14056, Laboratory furniture - Recommendations for design and installation
EN 14175-1, Fume cupboards - Part 1: Vocabulary
EN 14175-2:2003, Fume cupboards - Part 2: Safety and performance requirements
EN 14175-3:2019, Fume cupboards - Part 3: Type test methods
EN 14175-4, Fume cupboards - Part 4: On-site test methods
EN 14175-6, Fume cupboards - Part 6: Variable air volume fume cupboards
ISO 16170:2016, In situ test methods for high efficiency filter systems in industrial facilities
3 Terms and definitions
For the purposes of this document, the terms and definitions given in EN 14175-1, EN 14175-2:2003,
EN 14175-3:2019, EN 14175-4, EN 14175-6 and the following apply.
ISO and IEC maintain terminological databases for use in standardization at the following addresses:
• IEC Electropedia: available at https://www.electropedia.org/
• ISO Online browsing platform: available at https://www.iso.org/obp
3.1
abatement system
equipment dedicated to the removal or reduction of pollutants from releases from installation to air or
liquid
Note 1 to entry: Examples for abatement systems are filters, scrubbers or holding tanks.
5

---------------------- Page: 7 ----------------------
SIST EN 14175-8:2022
EN 14175-8:2022 (E)
3.2
activity
quantity A of radionuclide that disintegrates in a second, defined as:
At = ddN / t
( )

where
dN is the expectation value of the number of spontaneous nuclear transformations from the
given energy state in the time interval dt.
−1
Note 1 to entry: The SI unit for activity is reciprocal second (s ), termed becquerel (Bq).
Note 2 to entry: This definition is generally based on the definition of activity given in Council Directive
2013/59/Euratom.
3.3
chamber
materials that form the work space
3.4
contamination
unintended or undesirable presence of radioactive substances on surfaces or within solids, liquids or
gases or on the human body
Note 1 to entry: The term ‘contamination’ might have a connotation that is not intended. The term ‘contamination’
refers only to the presence of radioactivity, and gives no indication of the magnitude of the hazard involved.
[SOURCE: Council Directive 2013/59/Euratom, Chapter II, Article 4 (18) – modified, Note 1 to entry was
added]
3.5
decontamination
complete or partial removal of contamination by a deliberate physical, chemical or biological process
Note 1 to entry: This definition is intended to include a wide range of processes for removing contamination from
people, equipment and buildings, but to exclude the removal of radionuclides from within the human body or the
removal of radionuclides by natural weathering or migration processes, which are not considered to be
decontamination.
[SOURCE: IAEA SAFETY STANDARDS SERIES, Radiation Protection and Safety of Radiation Sources:
International Basic Safety Standards General Safety Requirements Part 3 (No. GSR Part 3)]
3.6
exposure
act of exposing or condition of being exposed to ionising radiation
Note 1 to entry: If exposure is taken place outside the body this is called external exposure. If exposure is taken
place inside the body, this is called internal exposure.
Note 2 to entry: This definition is generally based on the definition of exposure given in Council Directive
2013/59/Euratom.
6

---------------------- Page: 8 ----------------------
SIST EN 14175-8:2022
EN 14175-8:2022 (E)
3.7
ionizing radiation
energy transferred in the form of particles or electromagnetic waves of a wavelength of 100 nanometres
or less capable of producing ions directly or indirectly
15
Note 1 to entry: A wavelength of 100 nanometres corresponds to a frequency of 3 × 10 Hz or more.
Note 2 to entry: The definition of ionizing radiation is based on the definition given in Council Directive
2013/59/Euratom.
3.8
sealed source
radioactive source in which the radioactive material is permanently sealed in a capsule or incorporated
in a solid form with the objective of preventing, under normal conditions of use, any dispersion of
radioactive substances
[SOURCE: Council Directive 2013/59/Euratom, Chapter II, Article 4 (90)]
3.9
source
anything that can cause radiation exposure - such as by emitting ionizing radiation or by releasing
radioactive substances or radioactive material - and can be treated as a single entity for purposes of
protection and safety
[SOURCE: IAEA SAFETY STANDARDS SERIES, Radiation Protection and Safety of Radiation Sources:
International Basic Safety Standards General Safety Requirements Part 3 (No. GSR Part 3) – modified,
Note was deleted]
3.10
watertight
capable of preventing the penetration of water into or through the structure with a water pressure head
corresponding to that for which the surrounding structure is designed
[SOURCE: ISO 19904-1:2019, 3.62]
4 Dimensions
The dimensions of fume cupboards for work with radioactive materials shall be in accordance with
EN 14175-2 with the following supplement.
The internal workspace of the fume cupboard for work with radioactive materials should be the
minimum volumetric size necessary to perform the function for which the fume cupboard is provided.
Minimizing the internal dimensions will benefit cleaning and decontamination, but the space should be
large enough to accommodate and access all the equipment to be used.
5 Basic safety and performance objectives
The basic safety and performance objectives of fume cupboards for work with radioactive materials shall
be in accordance with EN 14175-2 with the following supplements.
Fume cupboards for work with radioactive materials shall protect employees and eventual public from
contamination and exposure to ionizing radiation as far as reasonably practicable.
Vapours shall be effectively exhausted to reduce the risk of an explosive or hazardous atmosphere within
the workspace.
7

---------------------- Page: 9 ----------------------
SIST EN 14175-8:2022
EN 14175-8:2022 (E)
Fume cupboards for work with radioactive materials shall be designed in accordance with the
environmental principle of using “best available techniques” for limiting discharges, emissions and waste.
It is recommended, that all fume cupboards for work with radioactive materials are performance tested
at the place of installation in accordance with EN 14175-4. On site test methods and the additional
requirements are described in this document.
6 Materials
6.1 General requirements
The materials used for fume cupboards for work with radioactive materials shall be in accordance with
EN 14175-2:2003, 6.1. The following requirements and the requirements given in 6.2 and 6.3 shall
further apply for fume cupboards for work with radioactive materials.
Fume cupboards shall be designed and constructed such that they do not readily become contaminated
and so that any contamination which does occur can be easily removed.
The workspace, the work surface and sash construction shall be such that the chosen materials are
suitable for the work to be carried out. Special attention should be paid to chemical and ionizing radiation
resistance, mechanical stability, structural design, ease of decontamination and cleaning, for further
reference see also ISO 8690.
Fume cupboards shall be made of materials which withstand the anticipated mechanical, chemical,
thermal and ionizing radiation stresses during expected use and shall not be easily combustible.
The materials of construction of these parts of the fume cupboards that are likely to come into contact
with the fumes and ionizing radiation shall be selected to suit the nature of the processes to be carried
out within the fume cupboard.
The choice of the appropriate material and the type of shielding needed is subject to safety assessment.
The fume cupboard shall be appropriately constructed to allow easy disassembly and disposal including,
where necessary, radioactive waste.
The construction of the fume cupboard shall be as such to allow for the possibility to add fixed external
shielding under the worktop and if required to the side walls, ceiling, back wall and front sash. The
amount and type of possible extra shielding will need to be specified by the user before the design is
finalised. If shielding is implemented, it should be ensured that it cannot dissociate from the fume
cupboard even in degraded conditions.
NOTE Using ceramic worktop and stoneware sinks can influence the results of contamination control
measurements because of natural radioactivity.
If seals are used, they shall be set and accessible so that they can be decontaminated for example before
dismantling.
When selecting the surface material, the chemical properties of the radionuclides to be used shall be
taken into account. Consult radiation protection expert in regard to compounds to be used and suitability
of construction materials of the fume cupboard.
6.2 Protective barrier
The choice of shielding materials used shall be based on energy, type of ionizing radiation (alpha, beta or
gamma radiation) and the activity of the radionuclide to be handled. Materials with a high atomic number
are appropriate shielding material when dealing with gamma emitters. For the handling of beta emitters,
materials with a low atomic number are to be used for shielding. The occurrence of radiation deceleration
(Bremsstrahlung) in the case of beta radiation shall be taken into consideration in the design of the
shielding.
8

---------------------- Page: 10 ----------------------
SIST EN 14175-8:2022
EN 14175-8:2022 (E)
Lead can be an appropriate material for gamma radiation shielding while plastic panes are suitable
materials
...

SLOVENSKI STANDARD
oSIST prEN 14175-8:2020
01-november-2020
Digestoriji - 8. del: Digestoriji za delo z radioaktivnimi snovmi
Fume cupboards - Part 8: Fume cupboards for work with radioactive materials
Abzüge - Teil 8: Abzüge für Arbeiten mit radioaktiven Substanzen
Ta slovenski standard je istoveten z: prEN 14175-8
ICS:
13.280 Varstvo pred sevanjem Radiation protection
71.040.10 Kemijski laboratoriji. Chemical laboratories.
Laboratorijska oprema Laboratory equipment
oSIST prEN 14175-8:2020 en,fr,de
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

---------------------- Page: 1 ----------------------
oSIST prEN 14175-8:2020

---------------------- Page: 2 ----------------------
oSIST prEN 14175-8:2020


DRAFT
EUROPEAN STANDARD
prEN 14175-8
NORME EUROPÉENNE

EUROPÄISCHE NORM

September 2020
ICS 13.280; 71.040.10
English Version

Fume cupboards - Part 8: Fume cupboards for work with
radioactive materials
 Abzüge - Teil 8: Abzüge für Arbeiten mit radioaktiven
Substanzen
This draft European Standard is submitted to CEN members for enquiry. It has been drawn up by the Technical Committee
CEN/TC 332.

If this draft becomes a European Standard, 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.

This draft European Standard was established by CEN 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, Turkey and
United Kingdom.

Recipients of this draft are invited to submit, with their comments, notification of any relevant patent rights of which they are
aware and to provide supporting documentation.

Warning : This document is not a European Standard. It is distributed for review and comments. It is subject to change without
notice and shall not be referred to as a European Standard.


EUROPEAN COMMITTEE FOR STANDARDIZATION
COMITÉ EUROPÉEN DE NORMALISATION

EUROPÄISCHES KOMITEE FÜR NORMUNG

CEN-CENELEC Management Centre: Rue de la Science 23, B-1040 Brussels
© 2020 CEN All rights of exploitation in any form and by any means reserved Ref. No. prEN 14175-8:2020 E
worldwide for CEN national Members.

---------------------- Page: 3 ----------------------
oSIST prEN 14175-8:2020
prEN 14175-8:2020 (E)
Contents Page
European foreword . 3
1 Scope . 4
2 Normative references . 4
3 Terms and definitions . 5
4 Dimensions. 6
5 Basic safety and performance objectives . 6
6 Materials . 6
6.1 General requirements . 6
6.2 Protective barrier . 7
6.3 Sash . 7
7 Safety requirements . 7
7.1 General requirements . 7
7.2 Construction . 8
7.2.1 Workspace . 8
7.2.2 Work surface . 8
7.2.3 Subbase . 9
7.2.4 Side walls . 10
7.2.5 Protective barrier . 10
7.2.6 Sash . 10
7.2.7 Abatement system . 10
8 Test methods . 11
8.1 Type testing . 11
8.2 Exhaust/waste air abatement system . 12
8.3 Testing methodologies and ventilation/containment performance . 12
9 Performance requirements . 12
10 Services . 12
10.1 General. 12
10.2 Drainage . 12
10.3 Liquids/water/cooling water . 12
10.4 Electric sockets . 12
11 User manual . 13
12 Marking and labelling . 13
13 Declaration of conformity . 13
Bibliography . 14

2

---------------------- Page: 4 ----------------------
oSIST prEN 14175-8:2020
prEN 14175-8:2020 (E)
European foreword
This document (prEN 14175-8:2020) has been prepared by Technical Committee CEN/TC 332
“Laboratory equipment”, the secretariat of which is held by DIN.
This document is currently submitted to the CEN Enquiry.
3

---------------------- Page: 5 ----------------------
oSIST prEN 14175-8:2020
prEN 14175-8:2020 (E)
1 Scope
This document specifies fume cupboards for work with unsealed radioactive materials with specific
requirements regarding radiation protection and it does not apply to glove boxes or hot cells not even
to α emitting radioisotopes.
The purpose of this document is to set out rules for the design and testing of fume cupboards for work
with unsealed radioactive materials, in order to provide guidelines for the planner, installer, operator,
assessor and the authorities.
NOTE If, when handling unsealed radioactive substances, radiopharmaceuticals are produced for use on
humans, the fume cupboards covered by this document are not sufficient.
Before using radioactive materials, a safety assessment needs to be performed. To find the maximum
activity allowed for every activity with radioactive material it is necessary to take into account the three
principles of radiological protection, namely justification, optimization, and the application of dose
limits, clarifying how they apply to radiation sources delivering exposure and to individuals receiving
exposure. Shield and abatement system required are also evaluated.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content
constitutes requirements 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.
EN 13150, Workbenches for laboratories in educational institutions - Dimensions, safety and durability
requirements and test methods
EN 14056, Laboratory furniture - Recommendations for design and installation
EN 14175-1, Fume cupboards - Part 1: Vocabulary
EN 14175-2:2003, Fume cupboards - Part 2: Safety and performance requirements
EN 14175-3:2019, Fume cupboards - Part 3: Type test methods
EN 14175-4, Fume cupboards - Part 4: On-site test methods
EN 14175-6:2006, Fume cupboards - Part 6: Variable air volume fume cupboards
IAEA SAFETY STANDARDS SERIES, Radiation Protection and Safety of Radiation Sources: International
Basic Safety Standards General Safety Requirements Part 3 (No. GSR Part 3)
4

---------------------- Page: 6 ----------------------
oSIST prEN 14175-8:2020
prEN 14175-8:2020 (E)
3 Terms and definitions
For the purposes of this document, the terms and definitions given in EN 14175-1 to EN 14175-6,
Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards (IAEA
SAFETY STANDARDS SERIES No. GSR Part 3) and the following apply.
ISO and IEC maintain terminological databases for use in standardization at the following addresses:
• IEC Electropedia: available at http://www.electropedia.org/
• ISO Online browsing platform: available at https://www.iso.org/obp/ui
3.1
activity
quantity A for an amount of radionuclide in a given energy state at a given time, defined as:
At = ddN / t
( )
where
dN is the expectation value of the number of spontaneous nuclear transformations from the
given energy state in the time interval dt.
−1
Note 1 to entry: The SI unit for activity is reciprocal second (s ), termed becquerel (Bq).
3.2
chamber
materials that form the work space
3.3
contamination
unintended or undesirable presence of radioactive substances on surfaces or within solids, liquids or
gases or on the human body;
Note 1 to entry: The term ‘contamination’ might have a connotation that is not intended. The term
‘contamination’ refers only to the presence of radioactivity, and gives no indication of the magnitude of the hazard
involved.
3.4
decontamination
complete or partial removal of contamination by a deliberate physical, chemical or biological process
Note 1 to entry: This definition is intended to include a wide range of processes for removing contamination from
people, equipment and buildings, but to exclude the removal of radionuclides from within the human body or the
removal of radionuclides by natural weathering or migration processes, which are not considered to be
decontamination.
3.5
dose
measure of the energy deposited by radiation in a target
3.6
exposure
act of exposing or condition of being exposed to ionising radiation emitted outside the body (external
exposure) or within the body (internal exposure)
5

---------------------- Page: 7 ----------------------
oSIST prEN 14175-8:2020
prEN 14175-8:2020 (E)
3.7
ionizing radiation
energy transferred in the form of particles or electromagnetic waves of a wavelength of
100 nanometres or less (a frequency of 3 × 1015 hertz or more) capable of producing ions directly or
indirectly
3.8
source
anything that may cause radiation exposure, such as by emitting ionizing radiation or by releasing
radioactive substances or radioactive material, and can be treated as a single entity for purposes of
protection and safety
3.8.1
sealed source
radioactive source in which the radioactive material is permanently sealed in a capsule or incorporated
in a solid form with the objective of preventing, under normal conditions of use, any dispersion of
radioactive substances
3.8.2
unsealed source
radioactive source in which the radioactive material is neither permanently sealed in a capsule nor
closely bonded and in a solid form
3.9
water tight
capable of preventing the penetration of water into or through the structure with a water pressure head
corresponding to that for which the surrounding structure is designed
[SOURCE: ISO 19904-1:2019(en), 3.62]
4 Dimensions
The dimensions shall be in accordance with EN 14175-2 with the following supplement.
The internal workspace of the fume cupboard should be the minimum volumetric size necessary to
perform the function for which the fume cupboard is provided.
Minimizing the size is better from a cleaning and decontamination point of view, but should be large
enough to accommodate all the equipment to be comfortably used.
5 Basic safety and performance objectives
The basic safety and performance objectives shall be in accordance with EN 14175-2 with the following
supplements.
Fume cupboards for work with radioactive materials shall protect employee and environment from
contamination and exposure to radiation.
6 Materials
6.1 General requirements
The materials used shall be in accordance with EN 14175-2:2003, 6.1. The following requirements
given below and under 6.2 and 6.3 shall further apply for fume cupboards for work with radioactive
materials.
6

---------------------- Page: 8 ----------------------
oSIST prEN 14175-8:2020
prEN 14175-8:2020 (E)
The workspace, the work surface and sash construction would be such that the chosen materials are
suitable for the work to be carried out. Special attention should be paid to chemical and radiation
resistance, mechanical stability, structural design, ease of decontamination and cleaning, for further
1
reference see also ISO 8690 .
NOTE The selection of material for the construction of the fume cupboard could be — powder coated steel,
austenitic steel, polypropylene, epoxy resin, laboratory benchtops made of clay ceramic materials, etc. depending
on the work to be carried out.
Fume cupboards shall be made of materials which withstand the anticipated mechanical, chemical,
thermal and radiation stresses during expected use and shall not be easily combustible.
The materials of construction of these parts of the fume cupboards that are likely to come into contact
with the fumes and radiation and shall be selected to suit the nature of the process carries out within
the fume cupboard.
The choice of the appropriate material and the type of shielding needed is subject to safety assessment.
Owing to an appropriate construction of the components an easy disassembly and disposal, if need be,
as radioactive waste, shall be ensured.
The construction of the fume cupboard shall be in a way to give the possibility to add fixed external
shielding under the worktop and if required to the side walls, ceiling and back wall. The amount and
type of possible extra shielding will need to be specified by the user before the design is finalised.
Ceramic worktop or stoneware sinks may only be used if the level of natural radioactive material is so
low that contamination control measurements are not affected.
When selecting the surface material, the chemical properties of the radio chemicals of the radionuclides
to be used shall be taken into account. For example, stainless steel surfaces using radio iodide
compounds and phosphates when using radio phosphorus compounds are not to be used.
6.2 Protective barrier
The shield materials used are based on energy, type of radiation (alpha, beta or gamma radiation) and
the activity of the radionuclide to be handled. Materials with a high atomic number are appropriate
shield material when dealing with gamma emitters. For the handling of beta emitters, materials with a
lower atomic number are to be used for shielding. The occurrence of radiation deceleration
(Bremsstrahlung) in the case of beta radiation shall be taken into consideration in the design of the
shielding.
NOTE Lead c
...

Questions, Comments and Discussion

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