ASTM C1831/C1831M-17(2022)
(Guide)Standard Guide for Gamma Radiation Shielding Performance Testing
Standard Guide for Gamma Radiation Shielding Performance Testing
SIGNIFICANCE AND USE
5.1 Shielding performance testing should be performed to verify analytical predictions of shielding effectiveness, compliance with design requirements, and determine the location(s) of shielding deficiencies that may require either supplemental shielding, design modification, or changes to operating methods and procedures to resolve.
5.2 Dose rates higher than adjacent shielding may be expected in the vicinity of master-slave manipulator penetrations as a result of cable or tape clearance requirements within the mechanisms where they pass through the shield walls. This is true even with supplemental shielding installed in the manipulator through tube.
5.3 Similar to manipulator penetrations, when sources are placed directly in front of penetrations and gaps resulting from access doors or panels, radiation levels directly on the other side of the gaps or penetrations may be higher than levels in adjacent shielding or analytical predictions. If these test configurations are representative of how the shielded enclosure will actually be operated (that is, the test configuration is representative of engineered source and normally occupied work locations) than the additional expense of designing or modifying the shielded enclosure should be considered if that location is normally occupied and will result in a significant increase of dose rates to personnel.
5.4 Frames around shield windows may have a higher potential for shielding deficiencies.
5.5 Shield walls constructed of concrete may be subject to the formation of void spaces that could result in diminished shielding performance.
5.6 Background radiation levels in the area where the dose measurement data are being gathered shall be monitored and their contribution to measured dose rates accounted for in the data analysis as part of the test report.
SCOPE
1.1 This guide identifies appropriate test methods for determining the sufficiency of radiological shielding for hot cells and shielded enclosures.
1.2 After constructing or modifying radiological shielding, it is necessary to verify that shielding performance meets or exceeds the shielding performance requirements. This is typically accomplished using sealed test sources of much less activity than the design basis. This allows for modifications or correction of any discrepancies identified before the commissioning of the hot cell.
1.3 The guidance and practices recommended by this guide are applicable to both new and existing shielded facilities and enclosures for evaluating shielding suitability and locating the existence of shine paths or other shielding anomalies that result from design, manufacture, or construction.
1.4 Two types of testing may be performed.
1.4.1 Shielding performance verification testing provides evidence that the shielding configuration is sufficient for meeting established performance criteria and for identifying deficiencies in the shielding configuration or components that may not have been addressed during design. Test results are expected to demonstrate that shielding performance meets or exceeds design criteria, not match the dose rates predicted analytically.
1.4.2 Shielding performance verification testing identifies shielding deficiencies (hot spots) in the installed configuration relative to adjacent shielding but does not demonstrate compliance with any quantitative shielding performance requirement.
1.5 Performance testing should be specified and performed to assess shielding adequacy with sources in all critical locations.
1.6 Requirements for shielding performance testing should be clearly defined in design basis or procurement documentation.
1.7 This guide is not applicable to neutron radiation shielding performance evaluations.
1.8 Units—The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, ea...
General Information
Standards Content (Sample)
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: C1831/C1831M − 17 (Reapproved 2022)
Standard Guide for
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Gamma Radiation Shielding Performance Testing
This standard is issued under the fixed designation C1831/C1831M; 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 1.7 This guide is not applicable to neutron radiation shield-
ing performance evaluations.
1.1 This guide identifies appropriate test methods for deter-
mining the sufficiency of radiological shielding for hot cells 1.8 Units—The values stated in either SI units or inch-
and shielded enclosures. pound units are to be regarded separately as standard. The
values stated in each system may not be exact equivalents;
1.2 After constructing or modifying radiological shielding,
therefore,eachsystemshallbeusedindependentlyoftheother.
it is necessary to verify that shielding performance meets or
Combining values from the two systems may result in noncon-
exceeds the shielding performance requirements. This is typi-
formance with the standard.
cally accomplished using sealed test sources of much less
1.8.1 Units for total activity should be given in Becquerel
activity than the design basis. This allows for modifications or
(Bq) or curies (Ci).
correction of any discrepancies identified before the commis-
1.8.2 Units for dose rate as measured during testing should
sioning of the hot cell.
be given in Sieverts (Sv/h) or rad/h.
1.3 The guidance and practices recommended by this guide
1.8.3 Distances and locations should be provided in centi-
are applicable to both new and existing shielded facilities and
metres or inches.
enclosures for evaluating shielding suitability and locating the
1.9 This standard does not purport to address all of the
existenceofshinepathsorothershieldinganomaliesthatresult
safety concerns, if any, associated with its use. It is the
from design, manufacture, or construction.
responsibility of the user of this standard to establish appro-
1.4 Two types of testing may be performed.
priate safety, health, and environmental practices and deter-
1.4.1 Shielding performance verification testing provides
mine the applicability of regulatory limitations prior to use.
evidence that the shielding configuration is sufficient for
1.10 This international standard was developed in accor-
meeting established performance criteria and for identifying
dance with internationally recognized principles on standard-
deficiencies in the shielding configuration or components that
ization established in the Decision on Principles for the
may not have been addressed during design. Test results are
Development of International Standards, Guides and Recom-
expected to demonstrate that shielding performance meets or
mendations issued by the World Trade Organization Technical
exceeds design criteria, not match the dose rates predicted
Barriers to Trade (TBT) Committee.
analytically.
1.4.2 Shielding performance verification testing identifies
2. Referenced Documents
shielding deficiencies (hot spots) in the installed configuration
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2.1 ASTM Standards:
relative to adjacent shielding but does not demonstrate com-
C859 Terminology Relating to Nuclear Materials
pliance with any quantitative shielding performance require-
ment.
3. Terminology
1.5 Performance testing should be specified and performed
3.1 For terms not defined in this guide, see Terminology
to assess shielding adequacy with sources in all critical
C859.
locations.
3.2 Definitions:
1.6 Requirements for shielding performance testing should
3.2.1 angular response sensitivity, n—the ability of an
be clearly defined in design basis or procurement documenta-
instrument or detector to detect radiation based on the angle of
tion.
incidence of the radiation on the instrument or detector.
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This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
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Cycle and is the direct responsibility of Subcommittee C26.14 on Remote Systems. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved July 1, 2022. Published July 2022. Originally approved contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
in 2017. Last previous edition approved in 2017 as C1831/C1831M – 17. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C1831_C1831M-17R22. the ASTM website.
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