ASTM C859-14a
(Terminology)Standard Terminology Relating to Nuclear Materials
Standard Terminology Relating to Nuclear Materials
SCOPE
1.1 This terminology standard contains terms, definitions, descriptions of terms, nomenclature, and explanations of acronyms and symbols specifically associated with standards under the jurisdiction of Committee C26 on Nuclear Fuel Cycle. This terminology may also be applicable to documents not under the jurisdiction of Committee C26, in which case this terminology may be referenced in those documents.
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Designation: C859 − 14a
StandardTerminology Relating to
1
Nuclear Materials
This standard is issued under the fixed designation C859; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope alpha radiation, n—is the spontaneous emission of an alpha
particle, composed of two protons and two neutrons with a
1.1 This terminology standard contains terms, definitions,
positive charge of plus two, during the nuclear transforma-
descriptions of terms, nomenclature, and explanations of acro-
tion process.
nyms and symbols specifically associated with standards under
DISCUSSION—An alpha particle is the same as a helium-4 atom with
thejurisdictionofCommitteeC26onNuclearFuelCycle.This
no electrons.
terminologymayalsobeapplicabletodocumentsnotunderthe
jurisdiction of Committee C26, in which case this terminology alteration, n—any change in the form, state, or properties of
may be referenced in those documents. materials.
alteration layer, n—in materials interaction with water,a
2. Terminology
layer of alteration phases at the surface of the specimen.
2 -2
absorbed dose, D, [L T ], n—absorbed dose is the mean DISCUSSION—Several distinct layers may form at the surface and
within cracks in the material. Layers may be composed of discrete
energy imparted by ionizing radiation to a unit mass of
crystallites.
specified material.
DISCUSSION—The SI unit for absorbed dose is the gray (Gy), defined
alteration mechanism, n—the series of fundamental chemical
as 1 J/kg.
or physical processes by which alteration occurs.
abundance sensitivity, n—in methods of chemical analysis,
alteration mode, n—for the prediction of long-term behavior
the ratio of the ion beam intensity of the major isotope, M,
of materials, a particular form of alteration, for example:
to the background current at the adjacent mass positions.
general corrosion, localized corrosion.
ion current at mass M
Abundance sensitivity 5 (1)
alteration phase, n—in materials interactions with their
ion current at M61
environment, a solid phase formed as a result of material
accelerated test, n—forthepredictionoflongtermbehaviorof
interactions, that replaces some amount of the original
materials, a test that results in an increase either in the rate
phase; may form by precipitation from solution of in-situ
of an alteration mode or in the extent of reaction progress,
transformation of a chemically altered solid.
when compared with expected service conditions.
alteration product, n—see alteration phase.
DISCUSSION—Changes in the expected alteration mechanism (s)
caused by the accelerated test conditions, if any, must be accounted for
aluminum-based spent nuclear fuel, n—irradiated nuclear
in the use of the accelerated test data.
fuelortargetelementsorassemblies,orboth,thatarecladin
accuracy, n—theclosenessofagreementbetweenameasure-
aluminum or aluminum-rich alloys.
ment result and an accepted reference. (E170)
DISCUSSION—The microstructures contain a continuous aluminum-
rich matrix with fissile-rich particles dispersed in this matrix.
–1
activity, A, [T ], n—the measure of the rate of spontaneous
aluminum-based spent nuclear fuel form or waste form,
nucleartransformationsofaradioactivematerial.TheSIunit
n—any metallic form produced from aluminum-based spent
for activity is the becquerel (Bq), defined as one transfor-
nuclear fuel and having a microstructure containing a
mation per second. The original unit for activity was the
10
continuous aluminum-rich matrix with uranium-rich par-
curie (Ci), defined as 3.7 × 10 transformations per second.
ticles dispersed in this matrix.
DISCUSSION—This term may include the fuel itself or the product
from the melt-dilute process.
1
ThisterminologyisunderthejurisdictionofASTMCommitteeC26onNuclear
FuelCycleandisthedirectresponsibilityofSubcommitteeC26.01onEditorialand
analog, n—for the prediction of long term behavior of
Terminology.
materials,amaterial,process,orsystemwhosecomposition,
Current edition approved June 15, 2014. Published July 2014. Originally
and environmental history are sufficiently similar to those
approved in 1977. Last previous edition approved in 2014 as C859–14. DOI:
10.1520/C0859-14a. anticipated for the materials, processes, or systems of
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C859 − 14a
interest to permit use of insight gained regarding its condi- chemisorbed water, n—in the drying of spent nuclear fuel,
tion or behavior to be applied to the material, process, or water that is bo
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM 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: C859 − 14 C859 − 14a
Standard Terminology Relating to
1
Nuclear Materials
This standard is issued under the fixed designation C859; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This terminology standard contains terms, definitions, descriptions of terms, nomenclature, and explanations of acronyms
and symbols specifically associated with standards under the jurisdiction of Committee C26 on Nuclear Fuel Cycle. This
terminology may also be applicable to documents not under the jurisdiction of Committee C26, in which case this terminology may
be referenced in those documents.
2. Terminology
2 -2
absorbed dose, D, [L T ], n—absorbed dose is the mean energy imparted by ionizing radiation to a unit mass of specified
material.
1
This terminology is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.01 on Editorial and
Terminology.
Current edition approved Jan. 15, 2014June 15, 2014. Published February 2014July 2014. Originally approved in 1977. Last previous edition approved in 20132014 as
C859 – 13a.C859 – 14. DOI: 10.1520/C0859-14.10.1520/C0859-14a.
DISCUSSION—
The SI unit for absorbed dose is the gray (Gy), defined as 1 J/kg.
abundance sensitivity, n—in methods of chemical analysis, the ratio of the ion beam intensity of the major isotope, M, to the
background current at the adjacent mass positions.
ion current at mass M
Abundance sensitivity 5 (1)
ion current at M61
accelerated test, n—for the prediction of long term behavior of materials, a test that results in an increase either in the rate of an
alteration mode or in the extent of reaction progress, when compared with expected service conditions.
DISCUSSION—
Changes in the expected alteration mechanism (s) caused by the accelerated test conditions, if any, must be accounted for in the use of the accelerated
test data.
accuracy, n—the closeness of agreement between a measurement result and an accepted reference. (E170)
–1
activity, A, [T ], n—the measure of the rate of spontaneous nuclear transformations of a radioactive material. The SI unit for
activity is the becquerel (Bq), defined as one transformation per second. The original unit for activity was the curie (Ci), defined
10
as 3.7 × 10 transformations per second.
alpha radiation, n—is the spontaneous emission of an alpha particle, composed of two protons and two neutrons with a positive
charge of plus two, during the nuclear transformation process.
DISCUSSION—
An alpha particle is the same as a helium-4 atom with no electrons.
alteration, n—any change in the form, state, or properties of materials.
alteration layer, n—in materials interaction with water, a layer of alteration phases at the surface of the specimen.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C859 − 14a
DISCUSSION—
Several distinct layers may form at the surface and within cracks in the material. Layers may be composed of discrete crystallites.
alteration mechanism, n—the series of fundamental chemical or physical processes by which alteration occurs.
alteration mode, n—for the prediction of long-term behavior of materials, a particular form of alteration, for example: general
corrosion, localized corrosion.
alteration phase, n—in materials interactions with their environment, a solid phase formed as a result of material interactions, that
replaces some amount of the original phase; may form by precipitation from solution of in-situ transformation of a chemically
altered solid.
alteration product, n—see alteration phase.
aluminum-based spent nuclear fuel, n—irradiated nuclear fuel or target elements or assemblies, or both, that are clad in
aluminum or aluminum-rich alloys.
DISCUSSION—
The microstructures contain a continuous aluminum-rich matrix with fissile-rich particles dispersed in this matrix.
aluminum-based spent nuclear fuel form or waste form, n—any metallic form produced from aluminum-based spent nuclear
fuel and having a microstructure containing a continuous aluminum-rich matrix with uranium-rich particles dispersed in this
matrix.
DISCUSSION—
This term may include the fuel itself or the product from the melt-dilute process.
a
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