SIST EN ISO 12807:2021

SLOVENSKI STANDARD
oSIST prEN ISO 12807:2020
01-november-2020
Varen prevoz radioaktivnih snovi - Preskušanje tesnjenja embalaže (ISO
12807:2018)
Safe transport of radioactive materials - Leakage testing on packages (ISO 12807:2018)
Kernbrennstofftechnologie - Sicherer Transport von radioaktivem Material -
Dichtheitsprüfung der Verpackung (ISO 12807:2018)
Sûreté des transports de matières radioactives - Contrôle de l'étanchéité des colis (ISO
12807:2018)
Ta slovenski standard je istoveten z: prEN ISO 12807
ICS:
13.280 Varstvo pred sevanjem Radiation protection
27.120.30 Cepljivi materiali in jedrska Fissile materials and nuclear
gorivna tehnologija fuel technology
oSIST prEN ISO 12807:2020 en,fr,de
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

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oSIST prEN ISO 12807:2020

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oSIST prEN ISO 12807:2020
INTERNATIONAL ISO
STANDARD 12807
Second edition
2018-09
Safe transport of radioactive
materials — Leakage testing on
packages
Sûreté des transports de matières radioactives — Contrôle de
l'étanchéité des colis
Reference number
ISO 12807:2018(E)
©
ISO 2018

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oSIST prEN ISO 12807:2020
ISO 12807:2018(E)

COPYRIGHT PROTECTED DOCUMENT
© ISO 2018
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
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Email: copyright@iso.org
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Published in Switzerland
ii © ISO 2018 – All rights reserved

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oSIST prEN ISO 12807:2020
ISO 12807:2018(E)

Contents Page
Foreword .v
Introduction .vi
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 1
4 Symbols and units . 4
5 Regulatory requirements . 7
5.1 Relevant regulations. 7
5.2 Regulatory containment requirements . 7
6 Procedure for meeting the requirements of this document . 7
6.1 General . 7
6.2 Quality management system . 8
6.3 Procedure . 8
6.3.1 General. 8
6.3.2 Determination of permissible activity release rates . 9
6.3.3 Determination of standardized leakage rates.10
6.3.4 Determination of permissible test leakage rates for each verification stage .10
6.3.5 Selection of appropriate test methods .10
6.3.6 Performance of test and record of results . .10
7 Determination of permissible activity release rates .10
7.1 Step 1: List the radioactive contents, A .
i 10
7.2 Step 2: Determine the total releasable activity, RI .
T 10
7.3 Step 3: Determine the maximum permissible activity release rates, R . 11
8 Determination of standardized leakage rates .11
8.1 General .11
8.2 Step 4: Determine the activity release rate due to permeation, RP . 12
8.3 Step 5: Determine the maximum permissible activity release rate due to leakage, RG . 12
8.4 Step 6: Determine the activity per unit volume of the containment system medium, C . 12
8.5 Step 7: Determine the maximum permissible volumetric leakage rate of the medium, L . 12
8.6 Step 8: Determine the maximum permissible equivalent capillary leak diameter, D . 12
8.7 Step 9: Determine the permissible standardized leakage rate, Q .
SLR 13
9 Containment-system verification requirements .13
9.1 Containment-system verification stages .13
9.1.1 General.13
9.1.2 Design verification .14
9.1.3 Fabrication verification .14
9.1.4 Preshipment verification .14
9.1.5 Periodic verification .15
9.1.6 Maintenance verification .15
9.2 Verification requirements .15
9.2.1 General.15
9.2.2 Step 10: Determine permissible test leakage rate for each verification
stage, Q , Q , Q Q Q and Q .
TDA TDN TF, TS, TP TM 15
9.2.3 Step 11: Select appropriate test methods .15
10 Leakage test procedure requirements .16
10.1 General .16
10.2 Step 12: Perform tests and record results .16
10.3 Test sensitivity .16
10.4 Test procedure requirements .16
10.4.1 General.16
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10.4.2 Testing .16
Annex A (informative) Preferred leakage test methods .17
Annex B (informative) Methods of calculation.31
Annex C (informative) Conversion tables .36
Annex D (informative) Worked examples .37
Annex E (informative) Rationale .72
Bibliography .85
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Foreword
ISO (the International Organization for Standardization) is a worldwide federation of national standards
bodies (ISO member bodies). The work of preparing International Standards is normally carried out
through ISO technical committees. Each member body interested in a subject for which a technical
committee has been established has the right to be represented on that committee. International
organizations, governmental and non-governmental, in liaison with ISO, also take part in the work.
ISO collaborates closely with the International Electrotechnical Commission (IEC) on all matters of
electrotechnical standardization.
The procedures used to develop this document and those intended for its further maintenance are
described in the ISO/IEC Directives, Part 1. In particular the different approval criteria needed for the
different types of ISO documents should be noted. This document was drafted in accordance with the
editorial rules of the ISO/IEC Directives, Part 2 (see www .iso .org/directives).
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. ISO shall not be held responsible for identifying any or all such patent rights. Details of
any patent rights identified during the development of the document will be in the Introduction and/or
on the ISO list of patent declarations received (see www .iso .org/patents).
Any trade name used in this document is information given for the convenience of users and does not
constitute an endorsement.
For an explanation on the voluntary nature of standards, the meaning of ISO specific terms and
expressions related to conformity assessment, as well as information about ISO's adherence to the
World Trade Organization (WTO) principles in the Technical Barriers to Trade (TBT) see the following
URL: www .iso .org/iso/foreword .html.
This document was prepared by Technical Committee ISO/TC 85, Nuclear energy, nuclear technologies,
and radiological protection, Subcommittee SC 5, Nuclear installations, processes and technologies.
This second edition cancels and replaces the first edition (ISO 12807:1996), which has been technically
revised.
In this document, the word “shall” denotes a requirement; the word “should” denotes a recommendation;
and the word “may” denotes permission, neither a requirement nor a recommendation. Imperative
statements also denote requirements. To conform with this document, all operations shall be performed
in accordance with its requirements, but not necessarily with its recommendations.
The words “can”, “could” and “might” denote possibility rather than permission.
The word “will” denotes that an event is certain to occur rather than a requirement.
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Introduction
The International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive
Material specify permitted release of radioactivity under normal and accident conditions of transport,
in terms of activity per unit of time, for Type B(U), Type B(M) and Type C packages used to transport
radioactive materials. Generally, it is not practical to measure activity release directly. The usual
method used is to relate activity release to non-radioactive fluid leakage, for which several leakages test
procedures are available. The appropriate procedure will depend on its sensitivity and its application
to a specific package.
The regulations specify permissible activity release for normal and accident conditions of transport.
These activity release limits can be expressed in maximum permissible activity release rates for the
radioactive material carried within a containment system.
In general, it is not feasible to demonstrate that the activity release limits are not exceeded by direct
measurement of activity release. In practice, the most common method to prove that a containment
system provides adequate containment is to carry out an equivalent gas leakage rate test.
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oSIST prEN ISO 12807:2020
INTERNATIONAL STANDARD ISO 12807:2018(E)
Safe transport of radioactive materials — Leakage testing
on packages
1 Scope
This document specifies gas leakage test criteria and test methods for demonstrating that packages
used to transport radioactive materials comply with the package containment requirements defined
in the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive
Material for:
— design verification;
— fabrication verification;
— preshipment verification;
— periodic verification;
— maintenance verification.
This document describes a method for relating permissible activity release of the radioactive contents
carried within a containment system to equivalent gas leakage rates under specified test conditions.
This approach is called gas leakage test methodology. However, in this document it is recognized that
other methodologies might be acceptable, provided that they demonstrate that any release of the
radioactive contents will not exceed the regulatory requirements, and subject to agreement with the
competent authority.
This document provides both overall and detailed guidance on the complex relationships between an
equivalent gas leakage test and a permissible activity release rate. Whereas the overall guidance is
universally agreed upon, the use of the detailed guidance shall be agreed upon with the competent
authority during the Type B(U), Type B(M) or Type C packages certification process.
It should be noted that, for a given package, demonstration of compliance is not limited to a single
methodology.
While this document does not require particular gas leakage test procedures, it does present minimum
requirements for any test that is to be used. It is the responsibility of the package designer or consignor
to estimate or determine the maximum permissible release rate of radioactivity to the environment
and to select appropriate leakage test procedures that have adequate sensitivity.
This document pertains specifically to Type B(U), Type B(M) or Type C packages for which the
regulatory containment requirements are specified explicitly.
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.
International Atomic Energy Agency (IAEA). Regulations for the Safe Transport of Radioactive Material
3 Terms and definitions
For the purposes of this document, the terms and definitions given in the International Atomic Energy
Agency (IAEA), Regulations for the Safe Transport of Radioactive Material and the following apply.
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ISO and IEC maintain terminological databases for use in standardization at the following addresses:
— ISO Online browsing platform: available at https: //www .iso .org/obp
— IEC Electropedia: available at https: //www .electropedia .org/
3.1
activity release rate
loss of radioactive contents per unit time through leaks or permeable walls of a containment system
3.2
blockage mechanism
mechanism by which radioactive material might be retained within a containment system due to
blockage of potential leakage paths by solid or liquid material
3.3
competent authority
any national or international authority designated or recognized as such for any purpose in connection
with the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive
Material and other applicable regulations
3.4
containment system
assembly of components of the packaging intended to retain the radioactive material during transport
3.5
gas leakage test methodology
method of specifying a gas leakage test which relates permissible activity release rates of the radioactive
contents carried within a containment system to equivalent gas leakage rates under specified test
conditions
3.6
leak
any unwanted opening or openings through a containment system that could permit the escape of the
contents
3.7
leakage
transfer of a material from the containment system to the environment through a leak or leaks
Note 1 to entry: See also permeation (3.14).
3.8
leakage rate
quantity of solid particles, liquids or gases passing through leaks per unit time
Note 1 to entry: The term leakage rate can refer to the radioactive material (gas, liquid, solid or any mixture of
these) or to the test fluid.
Note 2 to entry: The dimensions of the rate of solid leakage are mass divided by time. The dimensions of the
rate of liquid leakage can be mass divided by time or volume divided by time. The dimensions of the rate of gas
leakage are the product of pressure and volume (this is a mass-like unit) divided by time at a known temperature.
3.9
leaktight
general term indicating that a containment system meets the required level of containment for
particular contents
Note 1 to entry: See Clause 8 in Annex E.
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3.10
medium
any fluid, which might or might not be radioactive itself, which could carry radioactive material through
a leak or leaks
3.11
molecular flow
flow of gas through a leak under conditions such that the mean free path is greater that the largest
dimension of a transverse section of the leak
Note 1 to entry: The rate of molecular flow depends on the partial pressure gradient.
3.12
package
packaging together with its radioactive contents as presented for transport
3.13
packaging
assembly of components necessary to enclose the radioactive contents completely
3.14
permeation
passage of a fluid through a solid permeable barrier (even if there are no leaks) by adsorption-diffusion-
desorption mechanisms
Note 1 to entry: Permeation should not be considered as a release of activity unless the fluid itself is radioactive.
In this document, permeation is applied only to gases.
3.15
permeation rate
quantity of gases passing through permeable walls per unit time
Note 1 to entry: The permeation rate depends on the partial pressure gradient.
3.16
qualitative
refers to leakage test procedures which detect the presence of a leak but do not measure leakage rate or
total leakage
3.17
quantitative
leakage test procedures which measure total leakage rate(s) from a containment system or from
parts of it
3.18 Sensitivity
3.18.1
sensitivity of a leakage detector
minimum usable response of the detector to tracer fluid leakage, that is, the leakage rate that will
produce a repeatable change in the detector reading
3.18.2
sensitivity of a leakage test procedure
minimum detectable leakage rate that the test procedure is capable of detecting
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3.19
standardized leakage rate
SLR
leakage rate, evaluated under known conditions, normalized to the flow of dry air at reference conditions
5
of upstream pressure 1,013 × 10 Pa, downstream pressure 0,0 Pa and temperature of 298 K (25 °C)
3 −1
Note 1 to entry: The units for standardized leakage rate are written as Pa·m ·s SLR.
3.20
standardized helium leakage rate
SHeLR
helium leakage rate, evaluated under known conditions, normalized to the flow of dry helium at
5
reference conditions of upstream pressure 1,013 × 10 Pa, downstream pressure 0,0 Pa and temperature
of 298 K (25 °C)
3 −1
Note 1 to entry: The units for standardized helium leakage rate are written as Pa·m ·s (SHeLR).
3.21
test gas or tracer gas
gas that is used to detect leakage or measure leakage rates
3.22
viscous flow
continuous flow of gas through a leak under conditions such that the mean free path is very small in
comparison with the smallest dimension of a transverse section of the leak
Note 1 to entry: This flow may be either laminar or turbulent. Viscous flow depends upon total pressure gradient.
4 Symbols and units
The following symbols and units are used in this document.
Symbol Definition Unit
A Activity of radionuclide i Bq
i
A Quantity (activity) of radioactive material, other than special-form radioac- Bq
2
tive material, as defined in the applicable documents listed in the Interna-
tional Atomic Energy Agency (IAEA) Regulations for the Safe Transport of
Radioactive Material
A A value of radionuclide i Bq
2i 2
a Capillary length/leakage hole length m
−3
C Average activity per unit volume; the symbol is used to simplify Figure 1 and Bq·m
represents the use of either C or C
A N
−3
C Average activity per unit volume of the medium that could escape from the Bq·m
A
containment system under accident conditions of transport
−3
C Average activity per unit volume of the medium that could escape from the Bq·m
N
containment system under normal conditions of transport
D Capillary diameter/leakage hole diameter m
D Maximum permissible diameter; the symbol is used to simplify Figure 1 and m
represents the use of either D or D
A N
D Maximum permissible equivalent capillary leak diameter under accident m
A
conditions of transport
D Bubble diameter m
B
D Maximum permissible equivalent capillary leak diameter under normal m
N
conditions of transport
FC Release fraction of radionuclide i from the radioactive contents into the con- —
iA
tainment system under accident conditions of transport
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Symbol Definition Unit
FC Release fraction of radionuclide i from the radioactive contents into the con- —
iN
tainment system under normal conditions of transport
FE Fraction of radionuclide i which is available for release from the containment —
iA
system into the environment under accident conditions of transport
FE Fraction of radionuclide i which is available for release from the containment —
iN
system into the environment under normal conditions of transport
−2
g Acceleration due to gravity g = 9,81 m·s
−1 −2
g Constant g = 1 kg m N ·s
0 0
H Test duration s
h Liquid height m
3 −1
L Volumetric leakage rate m ·s
3 −1
L Maximum permissible volumetric leakage rate; the symbol is used to m ·s
simplify Figure 1 and represents the use of either L or L
A N
3 −1
L Maximum permissible volumetric leakage rate of the medium at pressure p , m ·s
A A
under accident conditions of transport
3 −1
L Maximum permissible volumetric leakage rate of the medium at pressure p , m ·s
N N
under normal conditions of transport
−1
M Relative molecular mass kg·mol
−1
M Relative molecular mass of component i kg·mol
i
−1
M Relative molecular mass of mixture kg·mol
mix
p Containment system pressure under accident conditions of transport Pa
A
p Containment system pressure under normal conditions of transport Pa
N
p Downstream pressure Pa
d
p Partial pressure of one component i of gas mixture Pa
i
p Total pressure of gas mixture Pa
mix
5
p Reference pressure p = 1,013 × 10 Pa
s s
p Partial pressure of tracer gas Pa
t
p Upstream pressure Pa
u
p Gas pressure at start of test Pa
1
p Gas pressure at end of test Pa
2
3 −1
Q Leakage rate Pa·m ·s
3 −1
Q Standardized leakage rate; the symbol is used to simplify Figure 1 and Pa·m ·s
SLR
represents the use of either Q or Q
A(SLR) N(SLR)
3 −1
Q The permissible leakage rate of the medium under accident conditions of Pa·m ·s
A
transport and is calculated from L
A
3 −1
Q The permissible standardized leakage rate (SLR) under accident conditions Pa·m ·s
A(SLR)
of transport
3 −1
Q Leakage rate for molecular flow Pa·m ·s
m
3 −1
Q Leakage rate for gas mixture Pa·m ·s
mix
3 −1
Q The permissible leakage rate of the medium under normal conditions of Pa·m ·s
N
transport and is calculated from L
N
3 −1
Q The permissible standardized leakage rate (SLR) under normal conditions of Pa·m ·s
N(SLR)
transport
3 −1
Q Permeation rate Pa·m ·s
p
3 −1
Q The permissible test leakage rate of the tracer or test gas that is related to Pa·m ·s
TDA
accident conditions of transport at the design verification stage and is deter-
mined from Q
A(SLR)
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Symbol Definition Unit
3 −1
Q The permissible test leakage rate of the tracer or test gas that is related to Pa·m ·s
TDN
normal conditions of transport at the design verification stage and is deter-
mined from Q
N(SLR)
3 −1
Q The permissible test leakage rate of the tracer gas at the fabrication verifica- Pa·m ·s
TF
tion stage
3 −1
Q The permissible test leakage rate of the tracer gas at the maintenance verifi- Pa·m ·s
TM
cation stage
3 −1
Q The permissible test leakage rate of the tracer gas at the periodic Pa·m ·s
TP
verification stage
3 −1
Q The permissible test leakage rate of the tracer gas at the preshipment Pa·m ·s
TS
vérification stage
3 −1
Q Leakage rate for viscous flow Pa·m ·s
v
−1 −1
R Universal gas constant R = 8,31 J mol K
−1
R Maximum permissible activity release rate; the symbol is used to simplify Bq·s
Figure 1 and represents the use of either R or R
A N
−1
R Maximum permissible activity release rate of the contents under accident Bq·s
A
conditions of transport
−1
R Maximum permissible activ
...