ASTM E170-08

Standard Terminology Relating to Radiation Measurements and Dosimetry

General Information

• Status: Historical
• Publication Date: 29-Feb-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 E170-05 - Standard Terminology Relating to Radiation Measurements and Dosimetry
• Effective Date: 01-Mar-2008
• Replaced By: ASTM E170-08a - Standard Terminology Relating to Radiation Measurements and Dosimetry
• Effective Date: 01-Apr-2008
• Referred By: ASTM F526-21 - Standard Test Method for Using Calorimeters for Total Dose Measurements in Pulsed Linear Accelerator or Flash X-ray Machines
• Effective Date: 01-Mar-2008
• Referred By: ASTM ISO/ASTM51401-13 - Standard Practice for Use of a Dichromate Dosimetry System
• Effective Date: 01-Mar-2008
• Referred By: ASTM ISO/ASTM51538-17 - Standard Practice for Use of the Ethanol-Chlorobenzene Dosimetry System
• Effective Date: 01-Mar-2008
• Referred By: ASTM D1879-06(2023) - Standard Practice for Exposure of Adhesive Specimens to Ionizing Radiation
• Effective Date: 01-Mar-2008
• Referred By: ASTM ISO/ASTM52303-15 - Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities
• Effective Date: 01-Mar-2008
• Referred By: ASTM ISO/ASTM51261-13(2020) - Standard Practice for Calibration of Routine Dosimetry Systems for Radiation Processing
• Effective Date: 01-Mar-2008
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 01-Mar-2008
• Referred By: ASTM E181-23 - Standard Guide for Detector Calibration and Analysis of Radionuclides in Radiation Metrology for Reactor Dosimetry
• Effective Date: 01-Mar-2008
• Referred By: ASTM E942-23 - Standard Guide for Investigating the Effects of Helium in Irradiated Metals
• Effective Date: 01-Mar-2008
• Referred By: ASTM ISO/ASTM51956-13 - Standard Practice for Use of Thermoluminescence-Dosimetry (TLD) Systems for Radiation Processing
• Effective Date: 01-Mar-2008
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 01-Mar-2008
• Referred By: ASTM ISO/ASTM51608-15(2022) - Standard Practice for Dosimetry in an X-Ray (Bremsstrahlung) Facility for Radiation Processing at Energies between 50 keV and 7.5 MeV
• Effective Date: 01-Mar-2008
• Referred By: ASTM ISO/ASTM52701-13(2020) - Standard Guide for Performance Characterization of Dosimeters and Dosimetry Systems for Use in Radiation Processing
• Effective Date: 01-Mar-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:E170–08
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 absorbeddoseisthegray(Gy),where1grayisequivalentto
3 the absorption of 1 joule per kilogram of the specified
1.1 ASTM Standards:
material (1 Gy = 1 J/kg). The mathematical relationship is
E380 Practice for the Use of the International System of
4 the quotient of de¯ by dm, where de¯ is the mean incremental
Units (SI) (The Modernized Metric System)
energyimpartedbyionizingradiationtomatterofincremen-
E456 Terminology Relating to Quality and Statistics
tal mass dm (see ICRU 33).
E706 Master Matrix for Light-Water Reactor Pressure
Vessel Surveillance Standards, E 706(0) D 5 de¯ dm (1)
/
E722 Practice for Characterizing Neutron Energy Fluence
DISCUSSION— The discontinued unit for absorbed dose is the rad (1
Spectra in Terms of an Equivalent Monoenergetic Neutron
rad = 100 erg/g = 0.01 Gy). Absorbed dose is sometimes referred to
Fluence for Radiation-Hardness Testing of Electronics
simply as dose. For a photon source under conditions of charged
E910 Test Method forApplication andAnalysis of Helium particle equilibrium, the absorbed dose, D, may be expressed as
follows:
Accumulation Fluence Monitors for Reactor Vessel Sur-
veillance, E706 (IIIC)
D5F· E· µ /r, (2)
en
2. Terminology
where:
2
F = particle fluence (particles/m ),
absorbed dose (D)—Quantity of ionizing radiation energy
E = energy of the ionizing radiation (J), and
2
impartedperunitmassofaspecifiedmaterial.TheSIunitof
µ /r = mass energy absorption coefficient (m /kg).
en
If bremsstrahlung production within the specified material is
negligible, the mass energy absorption coefficient (µ /r)is
en
1
ThisterminologyisunderthejurisdictionofASTMCommitteeE10onNuclear
equal to the mass energy transfer coefficient (µ /r), and
tr
Technology and Applications and is the direct responsibility of Subcommittee
absorbeddoseisequaltokermaif,inaddition,chargedparticle
E10.93 on Editorial.
Current edition approved March 1, 2008. Published April 2008. Originally
equilibrium exists.
approved in 1963. Last previous edition approved in 2005 as E170–05.
2
˙
Available from International Commission on Radiation Units and Measure- absorbed dose rate, D—the absorbed dose in a material per
ments (ICRU), 7910 Woodmont Ave., Suite 800, Bethesda, MD 20814.
incremental time interval, that is, the quotient of d D by d t
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
(see ICRU Report 33).
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
˙
D 5dD/dt (3)
the ASTM website.
−1
4
Withdrawn. SI unit: Gy·s .
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E170–08
DISCUSSION—Theabsorbed-doserateisoftenspecifiedintermsofthe
accepted as a measurement reference by a community of
average value of D over longer time intervals, for example, in units of
users.
−1 −1
Gy·min or Gy·h .
standard neutron field—a permanent and reproducible neu-
accuracy—the closeness of agreement between a measure- tron field with neutron fluence rate and energy spectra, and
their associated spatial and angular dist
...

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:E170–05 Designation:E170–08
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
E706Master Matrix for Light-Water Reactor PressureVessel Surveillance Standards 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
Forfor Radiation-Hardness Testing of Electronics
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,
E706 (IIIC)
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:
D5F· E· µ /r, (2)
en
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 Jan.March 1, 2005.2008. Published February 2005.April 2008. Originally approved in 1963. Last previous edition approved in 19992005 as
E170–99.E170–05.
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
Neutron Cross Sections for Reactor Dosimetry, International Atomic Energy Agency, Laboratory Activities, Vienna, 1978, Vol 1, p. 62.
4
Withdrawn.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E170–08
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 negligible, the mass energy absorption coefficient (µ /r) is equal to
en
the mass energy transfer coefficient (µ /r), and absorbed dose is equal to kerma if, in addition, charged particle equilibrium exists.
tr
˙
absorbeddoserate, D—theabsorb
...