ASTM C1572 C1572M-2017 Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities《遥控设备无水铅玻璃和充油铅玻璃辐射屏蔽窗部件的标准指.pdf

《ASTM C1572 C1572M-2017 Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities《遥控设备无水铅玻璃和充油铅玻璃辐射屏蔽窗部件的标准指.pdf》由会员分享，可在线阅读，更多相关《ASTM C1572 C1572M-2017 Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities《遥控设备无水铅玻璃和充油铅玻璃辐射屏蔽窗部件的标准指.pdf（40页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: C1572 10C1572/C1572M 17Standard Guide forDry Lead Glass and Oil-Filled Lead Glass RadiationShielding Window Components for Remotely OperatedFacilities1This standard is issued under the fixed designation C1572;C1572/C1572M; the number immediately following the designation indicatesthe ye

2、ar of original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of lastreapproval. A superscript epsilon () indicates an editorial change since the last revision or reapproval.1. Scope1.1 Intent:1.1.1 The intent of this standard is to provid

3、e guidance for the design, fabrication, quality assurance, inspection, testing,packaging, shipping, installation, and maintenance of radiation shielding window components. These window components includewall liner embedments, dry lead glass radiation shielding window assemblies, oil-filled lead glas

4、s radiation shielding windowassemblies, shielding wall plugs, barrier shields, view ports, and the installation/extraction table/device required for the installationand removal of the window components.1.2 Applicability:1.2.1 This standard is intended for those persons who are tasked with the planni

5、ng, design, procurement, fabrication,installation, and operation of the radiation shielding window components that may be used in the operation of hot cells, high levelcaves, mini-cells, canyon facilities, and very high level radiation areas.1.2.2 This standard applies to radiation shielding window

6、assemblies used in normal concrete walls, high-density concretewalls, 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 forInternational Systems, and defined, byvalues stated in SI units or inch-pound un

7、its are to be regarded separately as standard. Thevalues 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 innonconfor

8、mance with the standard. Common nomenclature for specifying some terms; specifically shielding, uses a combinationof 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

9、 list of the radiation source spectra and geometry information, typically required for shieldinganalysis.A2.1TableA2.1 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. A3Ann

10、ex 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 OwnerOperators 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 radiationshielding w

11、indow 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 desi

12、gns for the safety related issues discussed in theHazard 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 p

13、urposely used in lieu of “should” to stress the importance of thestatements 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 responsibilityof the user of this standard to establish appropriate

14、safety safety, health and healthenvironmental practices and determine theapplicability 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

15、approved Nov. 1, 2010Aug. 1, 2017. Published December 2010August 2017. Originally approved in 2004. Last previous edition approved in 20042010as C1572 - 04.C1572 10. DOI: 10.1520/C1572-10.10.1520/C1572_C1572M-17.This document is not an ASTM standard and is intended only to provide the user of an AST

16、M standard an indication of what changes have been made to the previous version. Becauseit 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 versionof the standard as published

17、by ASTM is to be considered the official document.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States11.4 This international standard was developed in accordance with internationally recognized principles on standardizationestablished in

18、the Decision on Principles for the Development of International Standards, Guides and Recommendations issuedby the World Trade Organization Technical Barriers to Trade (TBT) Committee.2. Referenced Documents2.1 Industry and National Consensus StandardsNationally recognized industry and consensus sta

19、ndards which may beapplicable in whole or in part to the design, fabrication, quality assurance, inspection, testing, packaging, shipping, installation andmaintenance of radiation shielding window components are referenced throughout this standard and include the following:2.2 ASTM Standards:2A27/A2

20、7M Specification for Steel Castings, Carbon, for General ApplicationA36/A36M Specification for Carbon Structural SteelA48/A48M Specification for Gray Iron CastingsA240/A240M Specification for Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for Pressure Vessels andfor General App

21、licationsA747/A747M Specification for Steel Castings, Stainless, Precipitation HardeningC859 Terminology Relating to Nuclear MaterialsC1533 Guide for General Design Considerations for Hot Cell EquipmentC1661 Guide for Viewing Systems for Remotely Operated FacilitiesD1533 Test Method for Water in Ins

22、ulating Liquids by Coulometric Karl Fischer TitrationE165 Practice for Liquid Penetrant Examination for General IndustryE170 Terminology Relating to Radiation Measurements and DosimetryE2024 Test Methods for Atmospheric Leaks Using a Thermal Conductivity Leak DetectorASTM/IEEE SI-10 Standard for Use

23、 of the International System of Units2.3 American Concrete Institute (ACI) Standards:3ACI C-31 Seismic Requirements2.4 American Institute of Steel Construction (AISC) Standard:4Manual of Steel Construction2.5 American National Standards Institute (ANSI) Standards:5ANSI Y 14 Engineering Drawing and R

24、elated Documentation PracticesANSI/ASME NQA-1 Quality Assurance Requirements for Nuclear Facility ApplicationsANSI/AWS A2.4 Standard Symbols for Welding, Brazing and Nondestructive ExaminationANSI/AWS B2.1 Specification for Welding Procedure and Performance QualificationANSI/AWS D1.1/D1.1M Structura

25、l Welding CodeSteelANSI/AWS D1.6/D1.6M Structural Welding CodeStainless SteelANSI/ISO/ASQ 9001 Quality Management Standard Requirements2.6 American Society for Nondestructive Testing (ASNT) Standards:6ASNT-SNT-TC-1A Recommended Practice for Qualification and Certification of Nondestructive Testing2.

26、7 Steel Structures Painting Council (SSPC):7SSPC-SP1 Solvent CleaningSSPC-SP6SSPC-SP5 Commercial White Metal Blast CleaningSSPC-P1SSPC-PA1 Paint Application SpecificationShop, Field, and Maintenance Painting of Steel2.8 Federal Standards (FS):8QQ-C-40 Caulking, Lead Wool, and F7 Lead Pig2.9 Federal

27、Regulations (FR):810 CFR20.1003 Definitions10 CFR50, Appendix B Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants10 CFR830.120 Subpart A Nuclear Safety Management, Quality Assurance Requirements2.10 International Building Code (IBC):8IBC Section 2314 Earthquake Regulat

28、ions2 For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.3 Available from American Concrete Institute (ACI), P.O.

29、Box 9094, Farmington Hills, MI 48333-9094, http:/www.concrete.org.4 Available from American Institute of Steel Construction (AISC), One E. Wacker Dr., Suite 700, Chicago, IL 60601-2001, http:/www.aisc.org.5 Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New Y

30、ork, NY 10036, http:/www.ansi.org.6 Available from American Society for Nondestructive Testing (ASNT), P.O. Box 28518, 1711 Arlingate Ln., Columbus, OH 43228-0518, http:/www.asnt.org.7 Available from Society for Protective Coatings (SSPC), 40 24th St., 6th Floor, Pittsburgh, PA 15222-4656, http:/www

31、.sspc.org.8 Available from U.S. Government Printing Office Superintendent of Documents, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.C1572/C1572M 1722.11 Other Standards:AESS (R) 44/70000/6 Atomic Energy Standard Specification for Shielding Glass9NCRP Report

32、 No. 82 SI Units in Radiation Protection and Measurements10ICRU Report 10b Physical Aspects of Irradiation113. Terminology3.1 General Considerations:3.1.1 The terminology employed in this guide conforms with industry practice insofar as practicable.3.1.2 For definitions of general terms used to desc

33、ribe nuclear materials, hot cells, and hot cell equipment, refer to TerminologyC859.3.2 Definitions:3.1.1 absorbed dose, D, L2T2, nabsorbed dose is the mean energy imparted by ionizing radiation to a mass of specifiedmaterial.3.1.1.1 DiscussionThe SI unit for absorbed dose is the gray (Gy), defined

34、as 1J/kg. NCRP-823.1.2 activity, A, T1, n in the nuclear industry, the measure of the rate of spontaneous nuclear transformations of aradioactive material.3.1.2.1 DiscussionThe SI unit for activity is the becquerel (Bq), defined as 1 transformation per second.3.1.2.2 DiscussionThe original unit for

35、activity was the curie (Ci), defined as 3.7 1010 transformations per second. NCRP-823.2.1 air dryer cartridge, na cloth bag containing moisture-absorbent crystals.3.2.1.1 DiscussionThe bag is inserted into the dryer assembly. The crystals are used to absorb moisture from the contained environment.3.

36、1.4 alpha radiation, nthe spontaneous emission of an alpha particle, composed of two protons and two neutrons with apositive charge of plus two, during the nuclear transformation process.3.1.4.1 DiscussionAn alpha particle is the same as a helium atom with no electrons.3.2.2 anti-reflection treatmen

37、t, na process applied to the surface of the glass that reduces reflection and increases the lighttransmission through the glass.3.2.2.1 DiscussionIt is often called a low-reflection treatment.3.2.3 as-built drawings, na set of drawings that reflect all of the changes that were incorporated into the

38、components duringthe manufacturing process since the original design.3.2.4 barrier shield assembly, nconsists of steel frames, gaskets, and a glass plate; typically cerium-stabilized, assembledtogether to form a see through barrier.3.2.4.1 Discussion9 HMSO, St. Clements House, 2-16 Colegate, Norwich

39、, NR3 1BQ. UK.10 Available from National Council of Radiation Protection and Measurements, 7910 Woodmont Avenue, Suite 400, Bethesda, MD 20814-3095.11 Available from International Commission on Radiation Units and Measurements, Inc., 7910 Woodmont Avenue, Suite 400, Bethesda, MD 20814-3095.C1572/C15

40、72M 173The assembly is mechanically fastened to the hot side of the wall liner to provide a gas tight containment barrier, which protectsthe window assembly from any radioactive contamination within the hot cell (alpha particles and other contaminates).3.2.5 barrier shield glass, na glass plate; typ

41、ically cerium stabilized that is used as a cover glass to see through and isolatethe window assembly from contamination.3.2.5.1 DiscussionIt is normally mounted in a barrier shield frame with gaskets to make up a barrier shield assembly.3.1.9 becquerel (Bq), T1, nthe SI unit of measure for activity,

42、 defined as one transformation per second.3.2.6 bellows, na flexible enclosure generally made of a pliable gasket material, which expands and contracts with thetemperature change of the inert gas and other components, maintaining a controlled atmosphere within the window assembly.3.2.6.1 DiscussionW

43、hen employed, the bellows is generally connected to the top of the expansion tank on an oil-filled window, and directly abovethe air dryer on the window housing of a dry window. The material of selection must be compatible with the environment, andwith the window components.3.1.11 beta radiation, na

44、n electron that was generated in the atomic nucleus during decay and has a negative charge of one.3.2.7 browning, nthe discoloration and darkening of glass to a brownish color due to excessive radiation exposure.3.2.8 bubbler system, na device used as a pressure relief, and constructed of an outer o

45、pen top container or chamber that isfilled with a liquid.3.2.8.1 DiscussionIt has a separate pressurized tube inserted into the liquid. When over-pressurization occurs in the tube, the gas bubbles out thebottom of the tube and up to the surface through the liquid.3.2.9 buffer seal, na specially conf

46、igured seal gasket used on a barrier shield.3.2.10 build-up factor, nfor radiation passing through a medium, buildup factor is the ratio of the total value of a specificradiation quantity (direct and scattered) measured as absorbed dose at any point within that medium to the contribution to thatquan

47、tity from the incident uncollided radiation reaching that point.3.2.10.1 DiscussionThe build-up factor increases with increased shielding thickness and is higher for low atomic number materials.3.1.16 canyon, nin the nuclear industry, a long, narrow, remotely operated radiological facility.3.1.16.1

48、DiscussionA large, heavily-shielded facility where nuclear material is processed or stored.3.2.11 cave, nin the nuclear hot cell applications, typically a small-scale hot cell facility.3.2.11.1 DiscussionThis term is sometimes used synonymously with hot cell.3.2.12 central viewing area, L2, nthe cen

49、tral viewing area of a glass slab or glass plate is that viewing area, circular orelliptical, of which the diameter of axis is 80 % of the maximum usable viewing window dimensions.3.2.13 cerium-stabilized glass, na glass type that contains a small percentage of cerium oxide to help stabilize the glass fromdiscoloration due to radiation exposure.3.2.13.1 DiscussionIt is often called non-browning glass.C1572/C1572M 1743.2.14 CMTR, nthe abbreviation for a Certified Material Test Report, which is a document that certifies the