ASTM E170-08a

Standard Terminology Relating to Radiation Measurements and Dosimetry

General Information

• Status: Historical
• Publication Date: 31-Mar-2008
• ICS: 01.040.17 - Metrology and measurement. Physical phenomena (Vocabularies)
• ICS: 17.240 - Radiation measurements
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.93 - Editorial

Relations

• Replaces: ASTM E170-08 - Standard Terminology Relating to Radiation Measurements and Dosimetry
• Effective Date: 01-Apr-2008
• Replaced By: ASTM E170-08b - Standard Terminology Relating to Radiation Measurements and Dosimetry
• Effective Date: 01-May-2008
• Referred By: ASTM E481-23 - Standard Practice for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver
• Effective Date: 01-Apr-2008
• Referred By: ASTM E942-23 - Standard Guide for Investigating the Effects of Helium in Irradiated Metals
• Effective Date: 01-Apr-2008
• Referred By: ASTM E720-23 - Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics
• Effective Date: 01-Apr-2008
• Referred By: ASTM E2215-19 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Apr-2008
• Referred By: ASTM E944-19 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
• Effective Date: 01-Apr-2008
• Referred By: ASTM E1297-18 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
• Effective Date: 01-Apr-2008
• Referred By: ASTM E705-18 - Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
• Effective Date: 01-Apr-2008
• Referred By: ASTM E821-16(2023) - Standard Practice for Measurement of Mechanical Properties During Charged-Particle Irradiation
• Effective Date: 01-Apr-2008
• Referred By: ASTM E3376-23 - Standard Practice for Calibration and Usage of Germanium Detectors in Radiation Metrology for Reactor Dosimetry
• Effective Date: 01-Apr-2008
• Referred By: ASTM ISO/ASTM51607-13 - Standard Practice for Use of the Alanine-EPR Dosimetry System
• Effective Date: 01-Apr-2008
• Referred By: ASTM E2006-22 - Standard Guide for Benchmark Testing of Light Water Reactor Calculations
• Effective Date: 01-Apr-2008
• Referred By: ASTM D1879-06(2023) - Standard Practice for Exposure of Adhesive Specimens to Ionizing Radiation
• Effective Date: 01-Apr-2008
• Referred By: ASTM ISO/ASTM51401-13 - Standard Practice for Use of a Dichromate Dosimetry System
• Effective Date: 01-Apr-2008

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:E170–08a
Standard Terminology Relating to
1
Radiation Measurements and Dosimetry
This standard is issued under the fixed designation E170; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
This terminology generally covers terms that apply to radiation measurements and dosimetry
associatedwithenergydepositionandradiationeffects,ordamage,inmaterialscausedbyinteractions
by high-energy radiation fields. The common radiation fields considered are X-rays, gamma rays,
electrons, alpha particles, neutrons, and mixtures of these fields. This treatment is not intended to be
exhaustive but reflects special and common terms used in technology and applications of interest to
CommitteeE10,asforexample,inareasofradiationeffectsoncomponentsofnuclearpowerreactors,
radiation hardness testing of electronics, and radiation processing of materials.
Thisterminologyusesrecommendeddefinitionsandconceptsofquantities,withunits,forradiation
measurements as contained in the International Commission on Radiation Units and Measurements
2
(ICRU) Report 33 on “Radiation Quantities and Units,”April 15, 1980. Those terms that are defined
essentiallyaccordingtotheterminologyofICRUReport33willbefollowedbyICRUinparentheses.
It should also be noted that the units for quantities used are the latest adopted according to the
International System of Units (SI).
1. Referenced Documents GUM Guide to the Expression of Uncertainty in Measure-
3 ment, ISO 1995
1.1 ASTM Standards:
VIM International Vocabulary of Basic and General Terms
E380 Practice for the Use of the International System of
4 in Metrology, ISO 1993
Units (SI) (The Modernized Metric System)
E456 Terminology Relating to Quality and Statistics
2. Terminology
E706 Master Matrix for Light-Water Reactor Pressure
absorbed dose (D)—Quantity of ionizing radiation energy
Vessel Surveillance Standards, E 706(0)
E722 Practice for Characterizing Neutron Energy Fluence impartedperunitmassofaspecifiedmaterial.TheSIunitof
absorbeddoseisthegray(Gy),where1grayisequivalentto
Spectra in Terms of an Equivalent Monoenergetic Neutron
Fluence for Radiation-Hardness Testing of Electronics the absorption of 1 joule per kilogram of the specified
material (1 Gy = 1 J/kg). The mathematical relationship is
E910 Test Method forApplication andAnalysis of Helium
Accumulation Fluence Monitors for Reactor Vessel Sur- the quotient of de¯ by dm, where de¯ is the mean incremental
energyimpartedbyionizingradiationtomatterofincremen-
veillance, E706 (IIIC)
5
1.2 ISO Standards: tal mass dm (see ICRU 33).
D 5 de¯ dm (1)
/
1
DISCUSSION— The discontinued unit for absorbed dose is the rad (1
ThisterminologyisunderthejurisdictionofASTMCommitteeE10onNuclear
Technology and Applications and is the direct responsibility of Subcommittee rad = 100 erg/g = 0.01 Gy). Absorbed dose is sometimes referred to
E10.93 on Editorial.
simply as dose. For a photon source under conditions of charged
Current edition approved April 1, 2008. Published April 2008. Originally
particle equilibrium, the absorbed dose, D, may be expressed as
approved in 1963. Last previous edition approved in 2008 as E170–08.
follows:
2
Available from International Commission on Radiation Units and Measure-
D5F· E· µ /r, (2)
ments (ICRU), 7910 Woodmont Ave., Suite 800, Bethesda, MD 20814.
en
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM where:
2
Standards volume information, refer to the standard’s Document Summary page on
F = particle fluence (particles/m ),
the ASTM website.
E = energy of the ionizing radiation (J), and
4
Withdrawn.
2
µ /r = mass energy absorption coefficient (m /kg).
5
en
Available from International Organization for Standardization (ISO), 1, ch. de
If bremsstrahlung production within the specified material is
la Voie-Creuse, Case postale 56, CH-1211, Geneva 20, Switzerland, http://
www.iso.ch.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E170–08a
negligible, the mass energy absorption coefficient (µ /r)is following classification of benchmark neutron fields for
en
6
equal to the mass energy transfer coefficient (µ /r), and reactor dosimetry has been made:
tr
absorbeddoseisequaltokermaif,inaddition,chargedparticle controlled neutron field—a neutron field physically well-
equilibrium exists. defined, and with some spectrum definition, employed for a
restricted set of validation experiments.
˙
absorbed dose rate,
...

This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:E170–08 Designation:E170–08a
Standard Terminology Relating to
1
Radiation Measurements and Dosimetry
This standard is issued under the fixed designation E170; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
This terminology generally covers terms that apply to radiation measurements and dosimetry
associatedwithenergydepositionandradiationeffects,ordamage,inmaterialscausedbyinteractions
by high-energy radiation fields. The common radiation fields considered are X-rays, gamma rays,
electrons, alpha particles, neutrons, and mixtures of these fields. This treatment is not intended to be
exhaustive but reflects special and common terms used in technology and applications of interest to
CommitteeE10,asforexample,inareasofradiationeffectsoncomponentsofnuclearpowerreactors,
radiation hardness testing of electronics, and radiation processing of materials.
Thisterminologyusesrecommendeddefinitionsandconceptsofquantities,withunits,forradiation
measurements as contained in the International Commission on Radiation Units and Measurements
2
(ICRU) Report 33 on “Radiation Quantities and Units,”April 15, 1980. Those terms that are defined
essentiallyaccordingtotheterminologyofICRUReport33willbefollowedbyICRUinparentheses.
It should also be noted that the units for quantities used are the latest adopted according to the
International System of Units (SI).
1. Referenced Documents
3
1.1 ASTM Standards:
4
E380 Practice for the Use of the International System of Units (SI) (The Modernized Metric System)
E456 Terminology Relating to Quality and Statistics
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E 706(0)
E722 Practice for Characterizing Neutron Energy Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence
for Radiation-Hardness Testing of Electronics
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,
E706 (IIIC)
5
1.2 ISO Standards:
GUM Guide to the Expression of Uncertainty in Measurement, ISO 1995
VIM International Vocabulary of Basic and General Terms in Metrology, ISO 1993
2. Terminology
absorbed dose (D)—Quantity of ionizing radiation energy imparted per unit mass of a specified material.The SI unit of absorbed
dose is the gray (Gy), where 1 gray is equivalent to the absorption of 1 joule per kilogram of the specified material (1 Gy = 1
J/kg).The mathematical relationship is the quotient of de¯ by dm, where de¯ is the mean incremental energy imparted by ionizing
radiation to matter of incremental mass dm (see ICRU 33).
D 5 de¯ dm (1)
/
DISCUSSION— The discontinued unit for absorbed dose is the rad (1 rad = 100 erg/g = 0.01 Gy).Absorbed dose is sometimes referred to simply as
dose. For a photon source under conditions of charged particle equilibrium, the absorbed dose, D, may be expressed as follows:
1
This terminology is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.93
on Editorial.
Current edition approved MarchApril 1, 2008. Published April 2008. Originally approved in 1963. Last previous edition approved in 20052008 as E170–058.
2
Available from International Commission on Radiation Units and Measurements (ICRU), 7910 Woodmont Ave., Suite 800, Bethesda, MD 20814.
3
ForreferencedASTMstandards,visittheASTMwebsite,www.astm.org,[e-mail] Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
4
Withdrawn.
5
Neutron Cross Sections for Reactor Dosimetry, International Atomic Energy Agency, Laboratory Activities, Vienna, 1978, Vol 1, p. 62.
5
Available from International Organization for Standardization (ISO), 1, ch. de la Voie-Creuse, Case postale 56, CH-1211, Geneva 20, Switzerland, http://www.iso.ch.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E170–08a
D5F· E· µ /r, (2)
en
where:
2
F = particle fluence (particles/m ),
E = energy of the ionizing radiation (J), and
2
µ /r = mass energy absorption coefficient (m /kg).
en
If bremsstrahlung production within the specified material is negligibl
...