ASTM C1572/C1572M-17

This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: C1572 − 10 C1572/C1572M − 17
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;C1572/C1572M; 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
1.1 Intent:
1.1.1 The 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, byvalues 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 ASTM/IEEE SI-10 Standard for Use of International System of Units. 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.
1.2.4 This standard identifies the special information required by the Manufacturer for the design of window components.
A1.1Table A1.1 shows a sample list of the radiation source spectra and geometry information, typically required for shielding
analysis. A2.1Table 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. A3Annex A3 shows general window configuration sketches.
Blank copies of A1.2Table A1.2 and A2.2Table A2.1 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.
1.2.6 Supplementary information on viewing systems in hot cells may be found in Guides C1533 and C1661.
1.3 Caveats:
1.3.1 Consideration shall be given when preparing the shielding window designs for the safety related issues discussed in the
Hazard Sources and Failure Modes, Section 11; such as dielectric discharge, over-pressurization, radiation exposure,
contamination, and overturning of the installation/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 safety, health and healthenvironmental practices and determine the
applicability of regulatory requirements prior to use.
1
This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.14 on Remote Systems.
Current edition approved Nov. 1, 2010Aug. 1, 2017. Published December 2010August 2017. Originally approved in 2004. Last previous edition approved in 20042010
as C1572 - 04.C1572 – 10. DOI: 10.1520/C1572-10.10.1520/C1572_C1572M-17.
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