ASTM E1005-03
(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)
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, and radioactive decay corrections (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 E 844. 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, E 706 (O)
E 853 Analysis and Interpretation of Light-Water Reactor Surveillance Results, E 706 (IA)
E 560 Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E 706 (IC)
E 693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E 706 (ID)
E 185 Practice for Conducting Surveillance Tests for Light-Water Nuclear Power Reactor Vessels, E 706 (IF)
E 1035 Practice for Determining Radiation Exposure for Nuclear Reactor Vessel Support Structures, E 706 (IG)
E 636 Practice for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
E 944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
E 1018 Guide for Application of ASTM Evaluated Cross Section and Data File, E 706 (IIB)
E 482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E 706 (IID)
E 2005 Guide for the Benchmark Testing of Reactor Vessel Dosimetryin Standard and Reference Neutron Fields
E 2006 Guide for the Benchmark Testing of Light Water Reactor Calcu...
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Standards Content (Sample)
NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
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Designation:E1005–03
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 (e) 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
1.2 This method is intended to be used in conjunction with
used to characterize the irradiation environment of the reactor
ASTM Guide E844, . The following existing or proposed
vessel and support structure. The principal measurement tech-
ASTM practices, guides, and methods are also directly in-
nique is high resolution gamma-ray spectrometry, although
volved in the physics-dosimetry evaluation of reactor vessel
X-rayphotonspectrometryandBetaparticlecountingareused
2
and support structure surveillance measurements:
to a lesser degree for specific RMs (1-29).
Master Matrix for Light-Water Reactor Pressure Vessel
1.1.1 The measurement procedures include corrections for
3
Surveillance Standards, E706 (O)
detector background radiation, random and true coincidence
E 853 Analysis and Interpretation of Light-Water Reactor
summing losses, differences in geometry between calibration
3
Surveillance Results, E706 (IA)
source standards and the RMs, self absorption of radiation by
E560PracticeforExtrapolatingReactorVesselSurveillance
the RM, other absorption effects, and radioactive decay cor-
3
Dosimetry Results, E706 (IC)
rections (1-10, 12-22).
E693PracticeforCharacterizingNeutronExposuresinIron
1.1.2 Specific activities are calculated by taking into ac-
and Low Alloy Steels in Terms of Displacements Per Atom
count the time duration of the count, the elapsed time between
3
(DPA), E706 (ID)
start of count and the end of the irradiation, the half life, the
E 185 Practice for Conducting Surveillance Tests for Light-
mass of the target nuclide in the RM, and the branching
3
Water Nuclear Power Reactor Vessels, E706 (IF)
intensities of the radiation of interest. Using the appropriate
E1035 Practice for Determining Radiation Exposure for
half life and known conditions of the irradiation, the specific
3
Nuclear Reactor Vessel Support Structures, E706 (IG)
activities may be converted into corresponding reaction rates
E 636 Practice for Conducting Supplemental Surveillance
(24-30).
3
Tests for Nuclear Power Reactor Vessels, E706 (IH)
1.1.3 Procedures for calculation of reaction rates from the
E 944 Guide for Application of Neutron Spectrum Adjust-
radioactivity measurements and the irradiation power time
3
ment Methods in Reactor Surveillance, E706 (IIA)
history are included. A reaction rate can be converted to
E 1018 Guide for Application of ASTM Evaluated Cross
neutron fluence rate and fluence using the appropriate integral
3
Section and Data File, E706 (IIB)
cross section and effective irradiation time values, and, with
E 482 Guide forApplication of Neutron Transport Methods
other reaction rates can be used to define the neutron spectrum
3
for Reactor Vessel Surveillance, E706 (IID)
through the use of suitable computer programs (24-30).
E 2005 Guide for the Benchmark Testing of Reactor Vessel
Dosimetryin Standard and Reference Neutron Fields
1
This method is under the jurisdiction of ASTM Committee E10 on Nuclear
E 2006 Guide for the Benchmark Testing of Light Water
Technology and Applications and is the direct responsibility of Subcommittee
Reactor Calculations
E10.05 on Nuclear Radiation Metrology.
Current edition approved Feb. 10, 2003. Published May 2003. Originally
approved in 1997. Last previous edition approved in 1997 as E1005–97.
2 3
The boldface numbers in parentheses refer to the li
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