ASTM E1005-10
(Test Method)Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
SIGNIFICANCE AND USE
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.
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 (35) 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 (23-29, 36-39).
SCOPE
1.1 This method describes general 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 11, 24-27. 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 (1-10, 12-22).
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 (24-30).
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 (24-30).
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 (24-30).
1.2 This method is intended to be used in conjunction with ASTM Guide E844. The following existing or proposed ASTM practices, guides, and methods are also directly involved in the physics-dosimetry evaluation of reactor vessel and support structure surveillance measurements:
Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706 (O)
E853 Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA)
E693 Practice for Characterizing Neutron Exposures in Iron and Lo...
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Designation: E1005 − 10
StandardTest Method for
Application and Analysis of Radiometric Monitors for
1
Reactor Vessel Surveillance, E 706 (IIIA)
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 Thismethoddescribesgeneralproceduresformeasuring
since many parameters, and their respective uncertainties,
the specific activities of radioactive nuclides produced in
required for calculation of absolute reaction rates are common
radiometric monitors (RMs) by nuclear reactions induced
toboththebenchmarkandtestmeasurementsandthereforeare
during surveillance exposures for reactor vessels and support
self canceling.The benchmark equivalent fluence rates, for the
structures. More detailed procedures for individual RMs are
environment tested, can be calculated from a direct ratio of the
provided in separate standards identified in 2.1 and in Refs 11,
measured saturated activities in the two environments and the
24-27. The measurement results can be used to define corre-
certified benchmark fluence rate (24-30).
sponding neutron induced reaction rates that can in turn be
used to characterize the irradiation environment of the reactor
1.2 This method is intended to be used in conjunction with
vessel and support structure. The principal measurement tech-
ASTMGuideE844.ThefollowingexistingorproposedASTM
nique is high resolution gamma-ray spectrometry, although
practices,guides,andmethodsarealsodirectlyinvolvedinthe
X-rayphotonspectrometryandBetaparticlecountingareused
physics-dosimetry evaluation of reactor vessel and support
2
to a lesser degree for specific RMs (1-29).
structure surveillance measurements:
1.1.1 The measurement procedures include corrections for
Master Matrix for Light-Water Reactor Pressure Vessel
3
detector background radiation, random and true coincidence
Surveillance Standards, E706 (O)
summing losses, differences in geometry between calibration
E853 Analysis and Interpretation of Light-Water Reactor
source standards and the RMs, self absorption of radiation by 3
Surveillance Results, E706 (IA)
theRM,otherabsorptioneffects,radioactivedecaycorrections,
E693 Practice for Characterizing Neutron Exposures in Iron
and burn out of the nuclide of interest (1-10, 12-22).
and Low Alloy Steels in Terms of Displacements Per Atom
1.1.2 Specific activities are calculated by taking into ac-
3
(DPA), E706 (ID)
count the time duration of the count, the elapsed time between
E185 Practice for Conducting Surveillance Tests for Light-
start of count and the end of the irradiation, the half life, the
3
Water Nuclear Power Reactor Vessels, E706 (IF)
mass of the target nuclide in the RM, and the branching
E1035 Practice for Determining Radiation Exposure for
intensities of the radiation of interest. Using the appropriate
3
Nuclear Reactor Vessel Support Structures, E706 (IG)
half life and known conditions of the irradiation, the specific
E636 Practice for Conducting Supplemental Surveillance
activities may be converted into corresponding reaction rates
3
Tests for Nuclear Power Reactor Vessels, E706 (IH)
(24-30).
1.1.3 Procedures for calculation of reaction rates from the E944 Guide for Application of Neutron Spectrum Adjust-
3
ment Methods in Reactor Surveillance, E706 (IIA)
radioactivity measurements and the irradiation power time
history are included. A reaction rate can be converted to
E1018 Guide for Application of ASTM Evaluated Cross
3
neutron fluence rate and fluence using the appropriate integral Section and Data File, E706 (IIB)
cross section and effective irradiation time values, and, with
E482 Guide for Application of Neutron Transport Methods
3
other reaction rates can be used to define the neutron spectrum
for Reactor Vessel Surveillance, E706 (IID)
through the use of suitable computer programs (24-30).
E2005 Guide for the Benchmark Testing of Reactor Vessel
Dosimetry in Standard and Reference Neutron Fields
1
This method is under the jurisdiction of ASTM Committee E10 on Nuclear
E2006 Guide for the Benchmark Testing of Light Water
Technology and Applicationsand is the direct responsibility of Subcommittee
Reactor Calculations
E10.05 on Nuclear Radiation Metrology.
Current edition approved Jan. 1, 2010. Published February 2010. Originally
´1
approved in 1997. Last previous edition approved in 2003 as E1005–03 . DOI:
10.1520/E1005-10.
3
2
The boldface numbers in parentheses refer to the list of references appended to The reference i
...
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:E 1005–84 (Reapproved 1991) Designation: E1005 – 10
Standard Test Method for
Application and Analysis of Radiometric Monitors for
1
Reactor Vessel Surveillance, E 706 (IIIA)
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 (ϵ) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This method describes general 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 11, 24-27. The
measurement results can be used to define corresponding neutron induced reaction rates whichthat can in turn be used to
characterize the irradiation environment of the reactor vessel and support structure. The principal measurement technique is high
resolutiongamma-rayspectrometry,althoughX-rayphotonspectrometryandBetaparticlecountingareusedtoalesserdegreefor
2
specific RMs (1-29).
1.1.1 The measurement procedures include corrections for detector background radiation, random and true coincidence
summinglosses,differencesingeometrybetweencalibrationsourcestandardsandtheRMs,selfabsorptionofradiationbytheRM,
other absorption effects, and radioactive decay corrections, and burn out of the nuclide of interest (1-10, 12-22).
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
radiationofinterest.Usingtheappropriatehalflifeandknownconditionsoftheirradiation,thespecificactivitiesmaybeconverted
into corresponding reaction rates (24-30).
1.1.3 Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history
areincluded.Areactionratecanbeconvertedtoneutronfluencerate(fluxdensity)andfluenceusingtheappropriateintegralcross
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 (24-30).
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 cancelling. The benchmark equivalent flux, 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 fluxfluence rate (24-30).
1.2 This method is intended to be used in conjunction withASTM Guides E 706 (IIC) and E 844E 844This method is intended
to be used in conjunction withASTM Guide E844. The following existing or proposedASTM practices, guides, and methods are
also directly involved in the physics-dosimetry evaluation of reactor vessel and support structure surveillance measurements:
3
E 706 (O) Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
3
E 706 (IA), E 853 Analysis and Interpretation of Light-Water Reactor Surveillance Results
3
E 706 (IC), E 560 Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results
3
E706(ID),E693PracticeforCharacterizingNeutronExposuresinFerriticSteelsinTermsofDisplacementsPerAtom(DPA)
3
E 706 (IE) Damage Correlation for Reactor Vessel Surveillance
3
E 706 (IF), E 185 Practice for Conducting Surveillance Tests for Light-Water Nuclear Power Reactor Vessels
3
E 706 (IG) Surveillance Tests for Nuclear Reactor Support Structures
3
E 706 (IH), E 636 Practice for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
3
E 706 (IIA), E 944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
3
E 706 (IIB), E 1018 Application of ASTM Evaluated Nuclear Data File (ENDF/A)—Cross Section and Uncertainty File
3
E 706 (IID), E 482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
1
This method is under the jurisdiction ofASTM Committee E-10 E10 on Nuclear Technology andApplications and
...
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