ASTM E1005-21
(Test Method)Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
SIGNIFICANCE AND USE
5.1 Radiometric monitors shall provide a proven passive dosimetry technique for the determination of neutron fluence rate (flux density), fluence, and spectrum in a diverse variety of neutron fields. These data are required to evaluate and estimate probable long-term radiation-induced damage to nuclear reactor structural materials such as the steel used in reactor pressure vessels and their support structures.
5.2 A number of radiometric monitors, their corresponding neutron activation reactions, and radioactive reaction products and some of the pertinent nuclear parameters of these RMs and products are listed in Table 1. Table 2 provides data (37) on the cumulative and independent fission yields of the important fission monitors. Not included in these tables are contributions to the yields from photo-fission, which can be especially significant for non-fissile nuclides (2-5, 27-29, 38-41). (A) All yield data are given as a percentage with associated uncertainties given as percentages of the percentage at the 1σ level.(B) For this fission yield evaluation (37), “Fast” indicates that the data was extracted from a wide range of reactor-based fission neutron spectra that can be characterized as having an average energy of ~0.4 MeV. Almost all of the fission reactions for U-238 and Th-232 occur above an effective threshold energy of ~1 MeV and, for Np-237, above ~0.2 MeV.
SCOPE
1.1 This test method describes procedures for measuring the specific activities of radioactive nuclides produced in radiometric monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures. More detailed procedures for individual RMs are provided in separate standards identified in 2.1 and in Refs (1-5).2 The measurement results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterize the irradiation environment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-ray spectrometry, although X-ray photon spectrometry and Beta particle counting are used to a lesser degree for specific RMs (1-29).
1.1.1 The measurement procedures include corrections for detector background radiation, random and true coincidence summing losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM, other absorption effects, radioactive decay corrections, and burn out of the nuclide of interest (6-26).
1.1.2 Specific activities are calculated by taking into account the time duration of the count, the elapsed time between start of count and the end of the irradiation, the half life, the mass of the target nuclide in the RM, and the branching intensities of the radiation of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be converted into corresponding reaction rates (2-5, 28-30).
1.1.3 Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history are included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section and effective irradiation time values, and, with other reaction rates can be used to define the neutron spectrum through the use of suitable computer programs (2-5, 28-30).
1.1.4 The use of benchmark neutron fields for calibration of RMs can reduce significantly or eliminate systematic errors since many parameters, and their respective uncertainties, required for calculation of absolute reaction rates are common to both the benchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environment tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified benchmark fluence rate (2-5, 28-30).
1.2 This test meth...
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This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the
Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
Designation: E1005 − 21
Standard Test Method for
Application and Analysis of Radiometric Monitors for
1
Reactor Vessel Surveillance
This standard is issued under the fixed designation E1005; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope 1.1.4 The use of benchmark neutron fields for calibration of
RMs can reduce significantly or eliminate systematic errors
1.1 Thistestmethoddescribesproceduresformeasuringthe
since many parameters, and their respective uncertainties,
specific activities of radioactive nuclides produced in radio-
required for calculation of absolute reaction rates are common
metric monitors (RMs) by nuclear reactions induced during
toboththebenchmarkandtestmeasurementsandthereforeare
surveillance exposures for reactor vessels and support struc-
self canceling.The benchmark equivalent fluence rates, for the
tures. More detailed procedures for individual RMs are pro-
2 environment tested, can be calculated from a direct ratio of the
vided in separate standards identified in 2.1 and in Refs (1-5).
measured saturated activities in the two environments and the
The measurement results can be used to define corresponding
certified benchmark fluence rate (2-5, 28-30).
neutron induced reaction rates that can in turn be used to
characterize the irradiation environment of the reactor vessel
1.2 This test method is intended to be used in conjunction
and support structure. The principal measurement technique is
with ASTM Guide E844 and existing or proposed ASTM
high resolution gamma-ray spectrometry, although X-ray pho-
practices, guides, and test methods that are also directly
tonspectrometryandBetaparticlecountingareusedtoalesser
involved in the physics-dosimetry evaluation of reactor vessel
degree for specific RMs (1-29).
and support structure surveillance measurements.
1.1.1 The measurement procedures include corrections for
1.3 The procedures in this test method are applicable to the
detector background radiation, random and true coincidence
measurement of radioactivity in RMs that satisfy the specific
summing losses, differences in geometry between calibration
constraints and conditions imposed for their analysis. More
source standards and the RMs, self absorption of radiation by
detailed procedures for individual RM monitors are identified
theRM,otherabsorptioneffects,radioactivedecaycorrections,
in 2.1 and in Refs 1-5 (see Table 1).
and burn out of the nuclide of interest (6-26).
1.1.2 Specific activities are calculated by taking into ac-
1.4 This test method, along with the individual RM monitor
count the time duration of the count, the elapsed time between
standard methods, are intended for use by knowledgeable
start of count and the end of the irradiation, the half life, the
persons who are intimately familiar with the procedures,
mass of the target nuclide in the RM, and the branching
equipment, and techniques necessary to achieve high precision
intensities of the radiation of interest. Using the appropriate
and accuracy in radioactivity measurements.
half life and known conditions of the irradiation, the specific
activities may be converted into corresponding reaction rates 1.5 The values stated in SI units are to be regarded as
standard. No other units of measurement are included in this
(2-5, 28-30).
1.1.3 Procedures for calculation of reaction rates from the standard,exceptfortheenergyunitsbasedontheelectronvolt,
keV and MeV, and the time units: minute (min), hour (h), day
radioactivity measurements and the irradiation power time
history are included. A reaction rate can be converted to (d), and year (a).
neutron fluence rate and fluence using the appropriate integral
1.6 This standard does not purport to address all of the
cross section and effective irradiation time values, and, with
safety concerns, if any, associated with its use. It is the
other reaction rates can be used to define the neutron spectrum
responsibility of the user of this standard to establish appro-
through the use of suitable computer programs (2-5, 28-30).
priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
1
This test method is under the jurisdiction ofASTM Committee E10 on Nuclear
1.7 This international standard was developed in accor-
Technology and Applications and is the direct responsibility of Subcommittee
dance with internationally recognized principles on standard-
E10.05 on Nuclear
...
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: E1005 − 16 E1005 − 21
Standard Test Method for
Application and Analysis of Radiometric Monitors for
1
Reactor Vessel Surveillance
This standard is issued under the fixed designation E1005; 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 test method describes procedures for measuring the specific activities of radioactive nuclides produced in radiometric
monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures. More
2
detailed procedures for individual RMs are provided in separate standards identified in 2.1 and in Refs (1-5). The measurement
results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterize the irradiation
environment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-ray
spectrometry, although X-ray photon spectrometry and Beta particle counting are used to a lesser degree for specific RMs (1-29).
1.1.1 The measurement procedures include corrections for detector background radiation, random and true coincidence summing
losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM, other
absorption effects, radioactive decay corrections, and burn out of the nuclide of interest (6-26).
1.1.2 Specific activities are calculated by taking into account the time duration of the count, the elapsed time between start of count
and the end of the irradiation, the half life, the mass of the target nuclide in the RM, and the branching intensities of the radiation
of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be converted into
corresponding reaction rates (2-5, 28-30).
1.1.3 Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history are
included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section and
effective irradiation time values, and, with other reaction rates can be used to define the neutron spectrum through the use of
suitable computer programs (2-5, 28-30).
1.1.4 The use of benchmark neutron fields for calibration of RMs can reduce significantly or eliminate systematic errors since
many parameters, and their respective uncertainties, required for calculation of absolute reaction rates are common to both the
benchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environment
tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified
benchmark fluence rate (2-5, 28-30).
1.2 This test method is intended to be used in conjunction with ASTM Guide E844. The following and existing or proposed ASTM
practices, guides, and test methods that are also directly involved in the physics-dosimetry evaluation of reactor vessel and support
structure surveillance measurements:measurements.
3
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706 (O)
1
This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05
on Nuclear Radiation Metrology.
Current edition approved Oct. 1, 2016Sept. 1, 2021. Published November 2016November 2021. Originally approved in 1997. Last previous edition approved in 20152016
as E1005 – 15.E1005 – 16. DOI: 10.1520/E1005-16.10.1520/E1005-21.
2
The boldface numbers in parentheses refer to the list of references appended to this method.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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E1005 − 21
3
E853 Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA)
E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA),
3
E706 (ID)
3
E185 Practice for Conducting Surveillance Tests for Light-Water Nuclear Power Reactor Vessels, E706 (IF)
3
E1035 Practice for Determining Radiation Exposure for Nuclear Reactor Vessel Support Str
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