ASTM E1005-97
(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 which 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 (flux density) 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 cancelling. The benchmark equivalent flux, for the environment tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified benchmark flux (24-30).
1.2 This method is intended to be used in conjunction with ASTM Guides E706 (IIC) and 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: E 706 (O) Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards E 706 (IA), E853 Analysis and Interpretation of Light-Water Reactor Surveillance Results E 706 (IC), E560 Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results E 706 (ID), E693 Practice for Characterizing Neutron Exposures in Ferritic Steels in Terms of Displacements Per Atom (DPA) E 706 (IE) Damage Correlation for Reactor Vessel Surveillance E 706 (IF), E185 Practice for Conducting Surveillance Tests for Light-Water Nuclear Power Reactor Vessels E 706 (IG) Surveillance Tests for Nuclear Reactor Support Structures E 706 (IH), E636 Practice for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E 706 (IIA), E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance E 706 (IIB), E1018 Application of ASTM Evaluated Nuclear Data File (ENDF/A)-Cross Section and Uncertainty File E 706 (IID), E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance E 706 (IIE) Benchmark Testing of Reactor Vessel Dosimetry E 706 (IIIB), E854 Test Method for Application and Analysis of S...
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Designation: E 1005 – 97
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 E 1005; 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope since many parameters, and their respective uncertainties,
required for calculation of absolute reaction rates are common
1.1 This method describes general procedures for measuring
to both the benchmark and test measurements and therefore are
the specific activities of radioactive nuclides produced in
self cancelling. The benchmark equivalent fluence rates, for the
radiometric monitors (RMs) by nuclear reactions induced
environment tested, can be calculated from a direct ratio of the
during surveillance exposures for reactor vessels and support
measured saturated activities in the two environments and the
structures. More detailed procedures for individual RMs are
certified benchmark fluence rate (24-30).
provided in separate standards identified in 2.1 and in Refs 11,
1.2 This method is intended to be used in conjunction with
24-27. The measurement results can be used to define corre-
3
ASTM Guide E 844, also referred to as E 706 (IIC) . The
sponding neutron induced reaction rates which can in turn be
following existing or proposed ASTM practices, guides, and
used to characterize the irradiation environment of the reactor
methods are also directly involved in the physics-dosimetry
vessel and support structure. The principal measurement tech-
evaluation of reactor vessel and support structure surveillance
nique is high resolution gamma-ray spectrometry, although
measurements:
X-ray photon spectrometry and Beta particle counting are used
2 E 706 (O) Master Matrix for Light-Water Reactor Pressure
to a lesser degree for specific RMs (1-29).
3
Vessel Surveillance Standards
1.1.1 The measurement procedures include corrections for
E 706 (IA), E 853 Analysis and Interpretation of Light-Water
detector background radiation, random and true coincidence
3
Reactor Surveillance Results
summing losses, differences in geometry between calibration
E 706 (IC), E 560 Practice for Extrapolating Reactor Vessel
source standards and the RMs, self absorption of radiation by
3
Surveillance Dosimetry Results
the RM, other absorption effects, and radioactive decay cor-
E 706 (ID), E 693 Practice for Characterizing Neutron
rections (1-10, 12-22).
Exposures in Ferritic Steels in Terms of Displacements Per
1.1.2 Specific activities are calculated by taking into ac-
3
Atom (DPA)
count the time duration of the count, the elapsed time between
E 706 (IE) Damage Correlation for Reactor Vessel Surveil-
start of count and the end of the irradiation, the half life, the
3
lance
mass of the target nuclide in the RM, and the branching
E 706 (IF), E 185 Practice for Conducting Surveillance Tests
intensities of the radiation of interest. Using the appropriate
3
for Light-Water Nuclear Power Reactor Vessels
half life and known conditions of the irradiation, the specific
E 706 (IG) Surveillance Tests for Nuclear Reactor Support
activities may be converted into corresponding reaction rates
3
Structures
(24-30).
E 706 (IH), E 636 Practice for Conducting Supplemental
1.1.3 Procedures for calculation of reaction rates from the
3
Surveillance Tests for Nuclear Power Reactor Vessels
radioactivity measurements and the irradiation power time
E 706 (IIA), E 944 Guide for Application of Neutron
history are included. A reaction rate can be converted to
3
Spectrum Adjustment Methods in Reactor Surveillance
neutron fluence rate (flux density) and fluence using the
E 706 (IIB), E 1018 Guide for Application of ASTM
appropriate integral cross section and effective irradiation time
3
Evaluated Cross Section and Data File
values, and, with other reaction rates can be used to define the
E 706 (IID), E 482 Guide for Application of Neutron
neutron spectrum through the use of suitable computer pro-
3
Transport Methods for Reactor Vessel Surveillance
grams (24-30).
E 706 (IIE) Benchmark Testing of Reactor Vessel Dosim-
1.1.4 The use of benchmark neutron fields for calibration of
3
etry
RMs can reduce significantly or eliminate systematic errors
E 706 (IIIB), E 854 Test Method for Application and
Analysis of Solid State Track Recorder (SSTR) Monitors for
1
3
This method is under the jurisdiction of ASTM Committee E-10 on Nuclear
Reactor Vessel Surveillance
Technology and Applications and is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
Current edition approved June 10, 1997. Publis
...
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