ASTM C 1831/C1831M : 2017 : R2022
Current
The latest, up-to-date edition.
Standard Guide for Gamma Radiation Shielding Performance Testing
Hardcopy , PDF
English
27-07-2022
Committee |
C 26
|
DocumentType |
Guide
|
Pages |
5
|
PublisherName |
American Society for Testing and Materials
|
Status |
Current
|
Supersedes |
1.1This guide identifies appropriate test methods for determining the sufficiency of radiological shielding for hot cells and shielded enclosures.
1.2After 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.
1.3The 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.
1.4Two types of testing may be performed.
1.4.1Shielding 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.
1.4.2Shielding 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.
1.5Performance testing should be specified and performed to assess shielding adequacy with sources in all critical locations.
1.6Requirements for shielding performance testing should be clearly defined in design basis or procurement documentation.
1.7This guide is not applicable to neutron radiation shielding performance evaluations.
1.8Units—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, each system shall be used independently of the other. Combining values from the two systems may result in nonconformance with the standard.
1.8.1Units for total activity should be given in Becquerel (Bq) or curies (Ci).
1.8.2Units for dose rate as measured during testing should be given in Sieverts (Sv/h) or rad/h.
1.8.3Distances and locations should be provided in centimetres or inches.
1.9This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
1.10This 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.
ASTM C 859 : 2023 | Standard Terminology Relating to Nuclear Materials |
ASTM C 859 : 2024 | Standard Terminology Relating to Nuclear Materials |
ASTM C 859 : 2022 : REV A | Standard Terminology Relating to Nuclear Materials |
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