ISO 12749-4:2015
(Main)Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 4: Dosimetry for radiation processing
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 4: Dosimetry for radiation processing
ISO 12749-4:2015 lists unambiguous terms and definitions for concepts for dosimetry related to radiation processing using gamma radiation, X-radiation, or accelerated electrons. It is intended to facilitate communication and promote common understanding.
Energie nucleaire, technologies nucleaires, et protection radiologique — Vocabulaire — Partie 4: Dosimétrie pour processus de radiation
General Information
Standards Content (Sample)
INTERNATIONAL ISO
STANDARD 12749-4
First edition
2015-08-15
Nuclear energy, nuclear technologies,
and radiological protection —
Vocabulary —
Part 4:
Dosimetry for radiation processing
Energie nucleaire, technologies nucleaires, et pmtection
radiologique — Vocabulaire —
Partie 4: Dosimetrie pour processue de radiation
Reference number
©
ISO 2015
© ISO 2015, Published in Switzerland
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ii © ISO 2015 – All rights reserved
Contents Page
Foreword .iv
Introduction .v
1 Scope . 1
2 Structure of the vocabulary . 1
3 Terms and definitions . 1
3.1 Terms related to dosimetry, dosimetry systems and ionizing radiation . 2
3.2 Terms related to dosimeters . 5
3.3 Terms related to radiation processing . 9
3.4 Terms related to measurement .15
Annex A (informative) Methodology used in the development of the vocabulary .19
Bibliography .25
Alphabetical Index .26
Foreword
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The committee responsible for this document is ISO/TC85 Nuclear energy, nuclear technologies, and
radiological protection.
ISO 12749 consists of the following parts, under the general title Nuclear energy, nuclear technologies,
and radiological protection — Vocabulary:
— Part 2: Radiological protection
— Part 3: Nuclear fuel cycle
— Part 4: Dosimetry for radiation processing
The following part is under preparation:
— Part 5: Nuclear reactors
The following part is planned:
— Part 1: General terminology
iv © ISO 2015 – All rights reserved
Introduction
This part of ISO 12749 provides terms and definitions for concepts for dosimetry related to radiation
processing using gamma radiation, X-radiation, or accelerated electrons. Concepts related to the
calibration and use of dosimetry systems for operational qualification and performance qualification
of commercial radiation processing facilities and for dose monitoring for quality assurance during the
routine processing of products are defined. Terminological data are taken from the ISO/ASTM standards
developed by ISO TC 85 and ASTM International Committee E61. Care is taken to ensure definitions are
consistent with other technically validated documents such as VIM, ICRU and GUM.
Unambiguous communication of nuclear energy concepts is crucial since serious consequences can arise
from misunderstandings with regard to standards related to equipment and materials used in nuclear
energy activities. Concepts dealing with dosimetry related to radiation processing and procedures for
preparation, testing, and using dosimetry systems to determine the absorbed dose are present in all
of the ISO/ASTM standards developed by WG3. To avoid misunderstandings, these concepts need to be
designated by common terms and described by harmonized definitions.
Conceptual arrangement of terms and definitions is based on concepts systems that show corresponding
relationships among nuclear energy concepts. Such arrangement provides users with a structured view
of the nuclear energy sector and will facilitate common understanding of all related concepts. Besides,
concepts systems and conceptual arrangement of terminological data will be helpful to any kind of user
because it will promote clear, accurate and useful communication.
INTERNATIONAL STANDARD ISO 12749-4:2015(E)
Nuclear energy, nuclear technologies, and radiological
protection — Vocabulary —
Part 4:
Dosimetry for radiation processing
1 Scope
This part of ISO 12749 lists unambiguous terms and definitions for concepts for dosimetry related to
radiation processing using gamma radiation, X-radiation, or accelerated electrons. It is intended to
facilitate communication and promote common understanding.
2 Structure of the vocabulary
The terminology entries are presented in the conceptual order of the English preferred terms. Both a
systematic index and an alphabetical index are included at the end of the standard. The structure of
each entry is in accordance with ISO 10241-1.
All the terms included in this part of ISO 12749 deal exclusively with dosimetry for radiation processing.
When selecting terms and definitions, special care has been taken to include the terms that need to
be defined, it means, either because the definitions are essential to the correct understanding of the
corresponding concepts or because some specific ambiguities need to be addressed.
The notes appended to certain definitions offer clarification or examples to facilitate understanding of
the concepts described. In certain cases, miscellaneous information is also included, for example, the
units in which a quantity is normally measured, recommended parameter values, references, etc.
According to the title, the vocabulary deals with concepts belonging to the general nuclear energy field
within which concepts in the dosimetry for radiation processing subfield are taking into account.
nuclear energy
dosimetry for radiation
processing
3.1 3.4
3.2 3.3
Terms related to
Terms related to dosimetry, Terms related to Terms related to
dosimetry systems, and measurement
dosimeters radiation processing
ionization radiation facilities
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
3.1 Terms related to dosimetry, dosimetry systems and ionizing radiation
3.1.1
dosimetry
measurement of absorbed dose by the use of a dosimetry system
[SOURCE: ISO/ASTM 52628:2013, 3.1.7]
3.1.2
absorbed dose
D
quotient of the dε by the dm, where the dε is the mean energy imparted by ionization radiation to
matter of mass dm
Note 1 to entry: It is expressed as
Dm=dε /d
Note 2 to entry: The special name for the unit of absorbed dose is gray (Gy), where 1 gray is equivalent to the
absorption of 1 J per kilogram of a specified material (1 Gy = 1 J / kg).
[SOURCE: ICRU 85a, 5.2.5, October 2011, modified]
Note 3 to entry: In most radiation processing applications, absorbed dose is in terms of absorbed dose to water.
3.1.3
dosimetry system
used for measuring absorbed dose, consisting of dosimeters, measurement instruments and their
associated reference standards, and procedures for the system’s use
[SOURCE: ISO/ASTM 52628:2013, 3.1.8, modified]
3.1.3.1
primary standard dosimetry system
designated or widely acknowledged as having the highest metrological qualities and whose value is
accepted without reference to other standards of the same quantity
[SOURCE: ISO/ASTM 52628:2013, 3.1.11, modified]
3.1.3.2
reference standard dosimetry system
generally having the highest metrological quality available at a given location or in a given organization,
from which measurements made there are derived
[SOURCE: ISO/ASTM 52628:2013, 3.1.13, modified]
3.1.3.3
routine dosimetry system
calibrated against a reference standard dosimetry system and used for routine absorbed dose
measurements, including dose mapping and process monitoring
[SOURCE: ISO/ASTM 52628:2013, 3.1.16, modified]
3.1.3.4
transfer standard dosimetry system
used as an intermediary to calibrate other dosimetry systems, usually routine dosimetry system
[SOURCE: ISO/ASTM 52628:2013, 3.1.18, modified]
2 © ISO 2015 – All rights reserved
3.1.4
ionizing radiation
consists of charged particles or uncharged particles, or both, that as a result of physical interaction,
creates ions by primary or secondary processes
Note 1 to entry: Charged particles could be positrons or electrons, and uncharged particles could be X-radiation
or gamma radiation.
[SOURCE: ASTM E170, 14a, modified]
3.1.4.1
gamma radiation
electromagnetic radiation emitted in the process of nuclear transition
[SOURCE: IEC 60050, modified]
3.1.4.1.1
activity
A
quotient of −dN by dt, where dN is the mean change in the number of nuclei in that energy state due to
spontaneous nuclear transformations in the time interval dt
Note 1 to entry: Activity of an amount of radionuclide in a particular energy state at a given time.
Note 2 to entry: It is expressed as
A = −dN/dt
−1 10
Note 3 to entry: The special name for the unit of activity is becquerel (Bq), where 1 Bq = 1 s and 1 Ci = 3,7×10
Bq.
[SOURCE: ICRU 85a, 6.2, October 2011, modified]
3.1.4.1.2
decay constant
λ
quotient of dN/N by dt, where dN/N is the mean fractional change in the number of nuclei in that energy
state due to spontaneous nuclear transformations in the time interval dt
Note 1 to entry: Decay constant of a radionuclide in a particular energy state.
Note 2 to entry: It is expressed as
dN/ N
λ =-
dt
[SOURCE: ICRU 85a, 6.1, October 2011, modified]
3.1.4.1.3
half-life
T
1/2
time taken for the activity of an amount of radionuclide to become half its initial value
Note 1 to entry: Half-life of a radionuclide in a particular energy state.
Note 2 to entry: T = ln2/λ, where λ is the decay constant (3.1.4.1.2).
1/2
3.1.4.2
X-radiation
X-ray
ionizing electromagnetic radiation, which includes both bremsstrahlung and the characteristic
radiation emitted when atomic electrons make transitions to more tightly bound states
Note 1 to entry: In radiation processing applications, the principal X-radiation is bremsstrahlung.
[SOURCE: ISO/ASTM 51608:2015, 3.2.1]
3.1.4.2.1
bremsstrahlung
broad-spectrum electromagnetic radiation emitted when an energetic charged particle is influenced by
a strong electric or magnetic field, such as that in the vicinity of an atomic nucleus
[SOURCE: ISO/ASTM 51608:2015, 3.1.4]
3.1.4.3
electron beam
stream of electrons generated by an electron accelerator
3.1.5
calibration
set of operations that establish, under specified conditions, the relationship between values of
quantities indicated by a measuring instrument or measuring system, or values represented by a
material measure or a reference material, and the corresponding values realized by standards
[SOURCE: ISO/ASTM 52628:2013, 3.1.3]
3.1.5.1
approved laboratory
recognized national metrology institute; or has been formally accredited to ISO/IEC 17025; or has a
quality system con
...
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