ASTM E1005-03e1
(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. Additional fission product reactions that may provide in situ photo fission information will be added to Table 1 as information is developed and verified (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 and in Refs , . 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 ().
1.1.1 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 (, ).
1.1.2 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 ().
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 ().
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().
General Information
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Standards Content (Sample)
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´1
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 (´) indicates an editorial change since the last revision or reapproval.
1
´ NOTE—The Referenced Documents were updated editorially in July 2006.
1. Scope cross section and effective irradiation time values, and, with
other reaction rates can be used to define the neutron spectrum
1.1 Thismethoddescribesgeneralproceduresformeasuring
through the use of suitable computer programs (24-30).
the specific activities of radioactive nuclides produced in
1.1.4 The use of benchmark neutron fields for calibration of
radiometric monitors (RMs) by nuclear reactions induced
RMs can reduce significantly or eliminate systematic errors
during surveillance exposures for reactor vessels and support
since many parameters, and their respective uncertainties,
structures. More detailed procedures for individual RMs are
required for calculation of absolute reaction rates are common
provided in separate standards identified in 2.1 and in Refs 11,
toboththebenchmarkandtestmeasurementsandthereforeare
24-27. The measurement results can be used to define corre-
self canceling.The benchmark equivalent fluence rates, for the
sponding neutron induced reaction rates that can in turn be
environment tested, can be calculated from a direct ratio of the
used to characterize the irradiation environment of the reactor
measured saturated activities in the two environments and the
vessel and support structure. The principal measurement tech-
certified benchmark fluence rate (24-30).
nique is high resolution gamma-ray spectrometry, although
1.2 This method is intended to be used in conjunction with
X-rayphotonspectrometryandBetaparticlecountingareused
2
ASTMGuideE844.ThefollowingexistingorproposedASTM
to a lesser degree for specific RMs (1-29).
practices,guides,andmethodsarealsodirectlyinvolvedinthe
1.1.1 The measurement procedures include corrections for
physics-dosimetry evaluation of reactor vessel and support
detector background radiation, random and true coincidence
structure surveillance measurements:
summing losses, differences in geometry between calibration
Master Matrix for Light-Water Reactor Pressure Vessel
source standards and the RMs, self absorption of radiation by
3
Surveillance Standards, E706 (O)
the RM, other absorption effects, and radioactive decay cor-
E853 Analysis and Interpretation of Light-Water Reactor
rections (1-10, 12-22).
3
Surveillance Results, E706 (IA)
1.1.2 Specific activities are calculated by taking into ac-
E560 Practice for Extrapolating Reactor Vessel Surveillance
count the time duration of the count, the elapsed time between
3
Dosimetry Results, E706 (IC)
start of count and the end of the irradiation, the half life, the
E693 Practice for Characterizing Neutron Exposures in Iron
mass of the target nuclide in the RM, and the branching
and Low Alloy Steels in Terms of Displacements Per Atom
intensities of the radiation of interest. Using the appropriate
3
(DPA), E706 (ID)
half life and known conditions of the irradiation, the specific
E185 Practice for Conducting Surveillance Tests for Light-
activities may be converted into corresponding reaction rates
3
Water Nuclear Power Reactor Vessels, E706 (IF)
(24-30).
E1035 Practice for Determining Radiation Exposure for
1.1.3 Procedures for calculation of reaction rates from the
3
Nuclear Reactor Vessel Support Structures, E706 (IG)
radioactivity measurements and the irradiation power time
E636 Practice for Conducting Supplemental Surveillance
history are included. A reaction rate can be converted to
3
Tests for Nuclear Power Reactor Vessels, E706 (IH)
neutron fluence rate and fluence using the appropriate integral
E944 Guide for Application of Neutron Spectrum Adjust-
3
ment Methods in Reactor Surveillance, E706 (IIA)
1
This method is under the jurisdiction of ASTM Committee E10 on Nuclear
E1018 Guide for Application of ASTM Evaluated Cross
Technology and Applications and is the direct responsibility of Subcommittee
3
Section and Data File, E706 (IIB)
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. DOI:
10.1520/E1005-03E01.
2 3
The boldface numbers in parentheses refer to the list of references appended to The reference in parentheses refers to Section 5 as well as Figs. 1 and 2 of
this method. Matrix E706.
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