ASTM C1572-2010 Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities《远程操作设备的干铅玻璃和充油铅玻璃辐射屏蔽窗设备标准指南》.pdf

《ASTM C1572-2010 Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities《远程操作设备的干铅玻璃和充油铅玻璃辐射屏蔽窗设备标准指南》.pdf》由会员分享，可在线阅读，更多相关《ASTM C1572-2010 Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities《远程操作设备的干铅玻璃和充油铅玻璃辐射屏蔽窗设备标准指南》.pdf（31页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: C1572 10Standard Guide forDry Lead Glass and Oil-Filled Lead Glass RadiationShielding Window Components for Remotely OperatedFacilities1This standard is issued under the fixed designation C1572; the number immediately following the designation indicates the year oforiginal adoption or,

2、in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript 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 provide guidance forthe design, fa

3、brication, quality assurance, inspection, testing,packaging, shipping, installation, and maintenance of radiationshielding window components. These window componentsinclude wall liner embedments, dry lead glass radiation shield-ing window assemblies, oil-filled lead glass radiation shieldingwindow a

4、ssemblies, shielding wall plugs, barrier shields, viewports, and the installation/extraction table/device required forthe installation and removal of the window components.1.2 Applicability:1.2.1 This standard is intended for those persons who aretasked with the planning, design, procurement, fabric

5、ation,installation, and operation of the radiation shielding windowcomponents that may be used in the operation of hot cells, highlevel caves, mini-cells, canyon facilities, and very high levelradiation areas.1.2.2 This standard applies to radiation shielding windowassemblies used in normal concrete

6、 walls, high-density con-crete walls, steel walls and lead walls.1.2.3 The system of units employed in this standard is themetric unit, also known as SI Units, which are commonly usedfor International Systems, and defined, by ASTM/IEEE SI-10Standard for Use of International System of Units. Commonno

7、menclature 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 re-quired by the Manufacturer for the design of window compo-nents. A1.1 shows a sample list of the radiation source spectraand

8、geometry information, typically required for shieldinganalysis. A2.1 shows a detailed sample list of specific datatypically required to determine the physical size, glass types,and viewing characteristics of the shielding window, or viewport. A3 shows general window configuration sketches. Blankcopi

9、es of A1.2 and A2.2 are found in the respective Annexesfor the OwnerOperators use.1.2.5 This standard is intended to be generic and to apply toa wide range of configurations and types of lead glass radiationshielding window components used in hot cells. It does notaddress glovebox, water, X-ray glas

10、s, or zinc bromide win-dows.1.2.6 Supplementary information on viewing systems in hotcells may be found in Guides C1533 and C1661.1.3 Caveats:1.3.1 Consideration shall be given when preparing theshielding window designs for the safety related issues dis-cussed in the Hazard Sources and Failure Modes

11、, Section 11;such as dielectric discharge, over-pressurization, radiationexposure, contamination, and overturning of the installation/extraction table/device.1.3.2 In many cases, the use of the word “shall” has beenpurposely used in lieu of “should” to stress the importance ofthe statements that hav

12、e been made in this standard.1.3.3 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory requireme

13、nts prior to use.2. Referenced Documents2.1 Industry and National Consensus StandardsNationally recognized industry and consensus standards whichmay be applicable in whole or in part to the design, fabrication,quality assurance, inspection, testing, packaging, shipping,installation and maintenance o

14、f radiation shielding windowcomponents are referenced throughout this standard and in-clude the following:2.2 ASTM Standards:2A27/A27M Specification for Steel Castings, Carbon, forGeneral Application1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct re

15、sponsibility of Subcommittee C26.14 on Remote Systems.Current edition approved Nov. 1, 2010. Published December 2010. Originallyapproved in 2004. Last previous edition approved in 2004 as C1572 - 04. DOI:10.1520/C1572-10.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact

16、 ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.A36/A36M Specification fo

17、r Carbon Structural SteelA48/A48M Specification for Gray Iron CastingsA240/A240M Specification for Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for PressureVessels and for General ApplicationsA747/A747M Specification for Steel Castings, Stainless,Precipitation HardeningC1533

18、Guide for General Design Considerations for HotCell EquipmentC1661 Guide for Viewing Systems for Remotely OperatedFacilitiesD1533 Test Method for Water in Insulating Liquids byCoulometric Karl Fischer TitrationE165 Practice for Liquid Penetrant Examination for GeneralIndustryE170 Terminology Relatin

19、g to Radiation Measurements andDosimetryE2024 Test Methods for Atmospheric Leaks Using a Ther-mal Conductivity Leak DetectorASTM/IEEE SI-10 Standard for Use of the InternationalSystem of Units2.3 American Concrete Institute (ACI) Standards:3ACI C-31 Seismic Requirements2.4 American Institute of Stee

20、l Construction (AISC) Stan-dard:4Manual of Steel Construction2.5 American National Standards Institute (ANSI) Stan-dards:5ANSI Y 14 Engineering Drawing and Related Documenta-tion PracticesANSI/ASME NQA-1 Quality Assurance Requirements forNuclear Facility ApplicationsANSI/AWS A2.4 Standard Symbols fo

21、r Welding, Brazingand Nondestructive ExaminationANSI/AWS B2.1 Specification for Welding Procedure andPerformance QualificationANSI/AWS D1.1/D1.1M Structural Welding CodeSteelANSI/AWS D1.6/D1.6M Structural Welding CodeStainless SteelANSI/ISO/ASQ 9001 Quality Management Standard Re-quirements2.6 Ameri

22、can Society for Nondestructive Testing (ASNT)Standards:6ASNT-SNT-TC-1A Recommended Practice for Qualifica-tion and Certification of Nondestructive Testing2.7 Steel Structures Painting Council (SSPC):7SSPC-SP1 Solvent CleaningSSPC-SP6 Commercial Blast CleaningSSPC-P1 Paint Application Specification2.

23、8 Federal Standards (FS):8QQ-C-40 Caulking, Lead Wool, and Lead Pig2.9 Federal Regulations (FR):810 CFR20.1003 Definitions10 CFR50, Appendix B Quality Assurance Criteria forNuclear Power Plants and Fuel Reprocessing Plants10 CFR830.120 Subpart A Nuclear Safety Management,Quality Assurance Requiremen

24、ts2.10 International Building Code (IBC):8IBC Section 2314 Earthquake Regulations2.11 Other Standards:AESS (R) 44/70000/6 Atomic Energy Standard Specifica-tion for Shielding Glass9NCRP Report No. 82 SI Units in Radiation Protection andMeasurements10ICRU Report 10b Physical Aspects of Irradiation113.

25、 Terminology3.1 Definitions:3.1.1 absorbed dose, D, L2T2, nabsorbed dose is themean energy imparted by ionizing radiation to a mass ofspecified material.3.1.1.1 DiscussionThe SI unit for absorbed dose is thegray (Gy), defined as 1J/kg. NCRP-823.1.2 activity, A, T1, nin the nuclear industry, themeasu

26、re of the rate of spontaneous nuclear transformations ofa radioactive 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 activity was thecurie (Ci), defined as 3.7 3 1010transformations per second.N

27、CRP-823.1.3 air dryer cartridge, na cloth bag containingmoisture-absorbent crystals.3.1.3.1 DiscussionThe bag is inserted into the dryerassembly. The crystals are used to absorb moisture from thecontained environment.3.1.4 alpha radiation, nthe spontaneous emission of analpha particle, composed of t

28、wo protons and two neutrons witha positive charge of plus two, during the nuclear transformationprocess.3.1.4.1 DiscussionAn alpha particle is the same as ahelium atom with no electrons.3.1.5 anti-reflection treatment, na process applied to thesurface of the glass that reduces reflection and increas

29、es thelight transmission through the glass.3.1.5.1 DiscussionIt is often called a low-reflection treat-ment.3.1.6 as-built drawings, na set of drawings that reflect allof the changes that were incorporated into the componentsduring the manufacturing process since the original design.3Available from

30、American Concrete Institute (ACI), P.O. Box 9094, FarmingtonHills, MI 48333-9094, http:/www.concrete.org.4Available from American Institute of Steel Construction (AISC), One E.Wacker Dr., Suite 700, Chicago, IL 60601-2001, http:/www.aisc.org.5Available from American National Standards Institute (ANS

31、I), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.6Available fromAmerican Society for Nondestructive Testing (ASNT), P.O. Box28518, 1711 Arlingate Ln., Columbus, OH 43228-0518, http:/www.asnt.org.7Available from Society for Protective Coatings (SSPC), 40 24th St., 6th Floor,Pittsb

32、urgh, PA 15222-4656, http:/www.sspc.org.8Available 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.9HMSO, St. Clements House, 2-16 Colegate, Norwich, NR3 1BQ. UK.10Available from National Council

33、of Radiation Protection and Measurements,7910 Woodmont Avenue, Suite 400, Bethesda, MD 20814-3095.11Available from International Commission on Radiation Units and Measure-ments, Inc., 7910 Woodmont Avenue, Suite 400, Bethesda, MD 20814-3095.C1572 1023.1.7 barrier shield assembly, nconsists of steel

34、frames,gaskets, and a glass plate; typically cerium-stabilized, as-sembled together to form a see through barrier.3.1.7.1 DiscussionThe assembly is mechanically fastenedto the hot side of the wall liner to provide a gas tightcontainment barrier, which protects the window assembly fromany radioactive

35、 contamination within the hot cell (alphaparticles and other contaminates).3.1.8 barrier shield glass, na glass plate; typically ceriumstabilized that is used as a cover glass to see through and isolatethe window assembly from contamination.3.1.8.1 DiscussionIt is normally mounted in a barriershield

36、 frame with gaskets to make up a barrier shield assembly.3.1.9 becquerel (Bq), T1, nthe SI unit of measure foractivity, defined as one transformation per second.3.1.10 bellows, na flexible enclosure generally made of apliable gasket material, which expands and contracts with thetemperature change of

37、 the inert gas and other components,maintaining a controlled atmosphere within the window assem-bly.3.1.10.1 DiscussionWhen employed, the bellows is gen-erally connected to the top of the expansion tank on anoil-filled window, and directly above the air dryer on thewindow housing of a dry window. Th

38、e material of selectionmust be compatible with the environment, and with thewindow components.3.1.11 beta radiation, nan electron that was generated inthe atomic nucleus during decay and has a negative charge ofone.3.1.12 browning, nthe discoloration and darkening ofglass to a brownish color due to

39、excessive radiation exposure.3.1.13 bubbler system, na device used as a pressure relief,and constructed of an outer open top container or chamber thatis filled with a liquid.3.1.13.1 DiscussionIt has a separate pressurized tubeinserted into the liquid. When over-pressurization occurs in thetube, the

40、 gas bubbles out the bottom of the tube and up to thesurface through the liquid.3.1.14 buffer seal, na specially configured seal gasketused on a barrier shield.3.1.15 build-up factor, nfor radiation passing through amedium, buildup factor is the ratio of the total value of aspecific radiation quanti

41、ty (direct and scattered) measured asabsorbed dose at any point within that medium to the contri-bution to that quantity from the incident uncollided radiationreaching that point.3.1.15.1 DiscussionThe build-up factor increases withincreased shielding thickness and is higher for low atomicnumber mat

42、erials.3.1.16 canyon, nin the nuclear industry, a long, narrow,remotely operated radiological facility.3.1.16.1 DiscussionA large, heavily-shielded facilitywhere nuclear material is processed or stored.3.1.17 cave, nin the nuclear hot cell applications, typi-cally a small-scale hot cell facility.3.1

43、.17.1 DiscussionThis term is sometimes used synony-mously with hot cell.3.1.18 central viewing area, L2, nthe central viewingarea of a glass slab or glass plate is that viewing area, circularor elliptical, of which the diameter of axis is 80 % of themaximum usable viewing window dimensions.3.1.19 ce

44、rium-stabilized glass, na glass type that containsa small percentage of cerium oxide to help stabilize the glassfrom discoloration due to radiation exposure.3.1.19.1 DiscussionIt is often called non-browning glass.3.1.20 CMTR, nthe abbreviation for a Certified MaterialTest Report, which is a documen

45、t that certifies the results oftests and analyses performed on the item provided.3.1.21 checks, nvery small fractures, or breakouts, nor-mally around the edge of a glass plate or glass slab.3.1.22 chip, na fragment broken from an edge or surface.3.1.23 clear view, L2, nthe physical size (length 3wid

46、th) of the smallest glass slab of all the glass components ina shielding window assembly.3.1.23.1 DiscussionThe actual clear view may be reducedby the method of retention of the glass in the window.3.1.24 cold side, nthe surface on a radiation shieldingwindow that is farthest from the radioactive so

47、urce, and usuallyis not subject to contamination.3.1.25 cold side load, na cold side load window assemblyis an assembly that is inserted into a wall liner or removed froma wall liner from the operator (cold side) of the hot cell.3.1.26 cover glass (hot or cold side), na glass platepositioned on the

48、hot or cold side of the window.3.1.26.1 DiscussionThe cover glass is often held in placewith a trim frame assembly and seal gaskets. This assemblyachieves a seal, which isolates the inner glass slabs from theexternal atmosphere and may also hold or contain the mineraloil within the window assembly.3

49、.1.27 curie (Ci), T1, nthe original unit of measure foractivity, defined as 3.7 3 1010transformations per second.3.1.28 density inch, na term used to describe the specificgravity of a shielding material multiplied by the thickness ofthat material in inches. The units are g/cc 3 (in.).3.1.29 desiccant air dryer, na device filled with crystalsand is used to remove moisture from a contained environment.3.1.30 dielectric discharge, nan instantaneous flow ofelectrical current from an irradiated glass component to thegroun