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ASTM C1572-04

(Guide)

Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities

Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities

SIGNIFICANCE AND USE
Radiation Shielding Window Components:
4.1.1 Radiation shielding window components operability and long-term integrity are concerns that originate during the design, and fabrication sequences. Such concerns can only be addressed, or are most efficiently addressed during one or the other of these stages. The operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.
4.1.2 This standard is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of radiation shielding window components.
SCOPE
1.1 Intent
1.1.1 This intent of this standard is to provide guidance for the design, fabrication, quality assurance, inspection, testing, packaging, shipping, installation and maintenance of radiation shielding window components. These window components include wall liner embedments, dry lead glass radiation shielding window assemblies, oil-filled lead glass radiation shielding window assemblies, shielding wall plugs, barrier shields, view ports, and the installation/extraction table/device required for the installation and removal of the window components.
1.2 Applicability
1.2.1 This standard is intended for those persons who are tasked with the planning, design, procurement, fabrication, installation, and operation of the radiation shielding window components that may be used in the operation of hot cells, high level caves, mini-cells, canyon facilities, and very high level radiation areas.
1.2.2 This standard applies to radiation shielding window assemblies used in normal concrete walls, high-density concrete walls, steel walls and lead walls.
1.2.3 The system of units employed in this standard is the metric unit, also known as SI Units, which are commonly used for International Systems, and defined, by ASTM/IEEE SI-10 Standard for Use of International System of Units. Common nomenclature for specifying some terms; specifically shielding, uses a combination of metric units and inch-pound units.
1.2.4 This standard identifies the special information required by the Manufacturer for the design of window components. A1.1 shows a sample list of the radiation source spectra and geometry information, typically required for shielding analysis. A2.1 shows a detailed sample list of specific data typically required to determine the physical size, glass types, and viewing characteristics of the shielding window, or view port. A3 shows general window configuration sketches. Blank copies of A1.2 and A2.2 are found in the respective Annexes for the Owner-Operator's use.
1.2.5 This standard is intended to be generic and to apply to a wide range of configurations and types of lead glass radiation shielding window components used in hot cells. It does not address glovebox, water, x-ray glass or zinc bromide windows.
1.3 Caveats
1.3.1 Consideration shall be given when preparing the shielding window designs for the safety related issues discussed in the Hazards Sources and Failure Modes, Section ; such as dielectric discharge, over-pressurization, radiation exposure, contamination, and overturning of the extraction table/device.
1.3.2 In many cases, the use of the word "shall" has been purposely used in lieu of "should" to stress the importance of the statements that have been made in this standard.
1.3.3 This 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 and health practices and determine the applicability of regulatory requirements prior to use.

General Information

Status
Historical
Publication Date
31-Dec-2003
ICS
13.280 - Radiation protection
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.14 - Remote Systems
Current Stage
Ref Project

Relations

Replaced By
ASTM C1572-10 - Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities
Effective Date
01-Nov-2010
Referred By
ASTM C1615/C1615M-17(2022) - Standard Guide for Mechanical Drive Systems for Remote Operation in Hot Cell Facilities
Effective Date
01-Jan-2004
Referred By
ASTM C1533-15(2022) - Standard Guide for General Design Considerations for Hot Cell Equipment
Effective Date
01-Jan-2004

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ASTM C1572-04 - Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated FacilitiesASTM C1572-04 - Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities
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Guide
ASTM C1572-04 - Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities
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Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: C1572 – 04
Standard Guide for
Dry Lead Glass and Oil-Filled Lead Glass Radiation
Shielding Window Components for Remotely Operated
1
Facilities
This standard is issued under the fixed designation C1572; 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. Scope copies of A1.2 and A2.2 are found in the respective Annexes
for the Owner–Operator’s use.
1.1 Intent:
1.2.5 Thisstandardisintendedtobegenericandtoapplyto
1.1.1 This intent of this standard is to provide guidance for
awiderangeofconfigurationsandtypesofleadglassradiation
the design, fabrication, quality assurance, inspection, testing,
shielding window components used in hot cells. It does not
packaging, shipping, installation and maintenance of radiation
addressglovebox,water,x-rayglassorzincbromidewindows.
shielding window components. These window components
1.3 Caveats:
include wall liner embedments, dry lead glass radiation shield-
1.3.1 Consideration shall be given when preparing the
ingwindowassemblies,oil-filledleadglassradiationshielding
shielding window designs for the safety related issues dis-
window assemblies, shielding wall plugs, barrier shields, view
cussed in the Hazards Sources and Failure Modes, Section 11;
ports, and the installation/extraction table/device required for
such as dielectric discharge, over-pressurization, radiation
the installation and removal of the window components.
exposure, contamination, and overturning of the extraction
1.2 Applicability:
table/device.
1.2.1 This standard is intended for those persons who are
1.3.2 In many cases, the use of the word “shall” has been
tasked with the planning, design, procurement, fabrication,
purposely used in lieu of “should” to stress the importance of
installation, and operation of the radiation shielding window
the statements that have been made in this standard.
componentsthatmaybeusedintheoperationofhotcells,high
1.3.3 This standard does not purport to address all of the
level caves, mini-cells, canyon facilities, and very high level
safety concerns, if any, associated with its use. It is the
radiation areas.
responsibility of the user of this standard to establish appro-
1.2.2 This standard applies to radiation shielding window
priate safety and health practices and determine the applica-
assemblies used in normal concrete walls, high-density con-
bility of regulatory requirements prior to use.
crete walls, steel walls and lead walls.
1.2.3 The system of units employed in this standard is the
2. Referenced Documents
metricunit,alsoknownasSIUnits,whicharecommonlyused
2.1 Industry and National Consensus Standards—
for International Systems, and defined, by ASTM/IEEE SI-
Nationally recognized industry and consensus standards which
10ASTM/IEEESI-10StandardforUseofInternationalSystem
maybeapplicableinwholeorinparttothedesign,fabrication,
of Units. Common nomenclature for specifying some terms;
quality assurance, inspection, testing, packaging, shipping,
specifically shielding, uses a combination of metric units and
installation and maintenance of radiation shielding window
inch-pound units.
components are referenced throughout this standard and in-
1.2.4 This standard identifies the special information re-
clude the following:
quired by the Manufacturer for the design of window compo-
2
2.2 ASTM Standards:
nents.A1.1 shows a sample list of the radiation source spectra
D1533 Test Method for Water in Insulating Liquids by
and geometry information, typically required for shielding
Coulometric Karl Fischer Titration
analysis. A2.1 shows a detailed sample list of specific data
E165 PracticeforLiquidPenetrantExaminationforGeneral
typically required to determine the physical size, glass types,
Industry
and viewing characteristics of the shielding window, or view
E170 TerminologyRelatingtoRadiationMeasurementsand
port.A3 shows general window configuration sketches. Blank
Dosimetry
1
2
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Cycle and is the direct responsibility of Subcommittee C26.14 on Remote Systems.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Current edition approved Jan. 1, 2004. Published January 2004. DOI: 10.1520/
Standards volume information, refer to the standard’s Document Summary page on
C1572-04.
the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
C1572 – 04
ASTM/IEEESI-10 Standard for U
...

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4.1.1 Radiation shielding window components operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns can only be addressed, or are most efficiently addressed, during one or the other of these stages. The operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.  
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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.  
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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.
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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.  
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5.1 This test method can be used to provide a measure of the reactivity of a material in a dilute solution in which the test response is dominated by the dissolution or leaching of the test specimen. It can be used to compare the dissolution or leaching behaviors of candidate radioactive waste forms and to study the reactions during static exposure to dilute solutions in which solution feed-back effects can be maintained negligible, depending on the test conditions.  
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SIGNIFICANCE AND USE
4.1 Radiation Shielding Window Components:  
4.1.1 Radiation shielding window components operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns can only be addressed, or are most efficiently addressed, during one or the other of these stages. The operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.  
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1.1 Intent:  
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1.2 Applicability:  
1.2.1 This standard is intended for those persons who are tasked with the planning, design, procurement, fabrication, installation, and operation of the radiation shielding window components that may be used in the operation of hot cells, high level caves, mini-cells, canyon facilities, and very high level radiation areas.  
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1.2.3 The values stated in 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. Common nomenclature for specifying some terms; specifically shielding, uses a combination of metric units and inch-pound units.  
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5.4 The test method is designed to include contributions of radiation dose to the wearer from secondary radiation emitted from the shielding material.
SCOPE
1.1 This test method establishes a procedure for measuring the relative reduction in the intensity of X-radiation provided by shielding garments to the human user under conditions simulating actual use.  
1.2 This test method provides a condition simulating X-rays generated between 60 and 130 kV that are scattered through an angle of 90° by a water equivalent material.  
1.3 This test method applies to both leaded and no-leaded radiation protective materials.  
1.4 This test method provides a method for inclusion of secondary radiations generated within the protective material into a more realistic evaluation of radiation protection.  
1.5 The values given in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This 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. Some specific hazards statements are given in Section 7.  
1.7 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.

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ASTM
ASTM C1831/C1831M-17(2022)(Guide)
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...

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