ASTM C1533-2008 Standard Guide for General Design Considerations for Hot Cell Equipment《热电解池的通用设计方法标准指南》.pdf

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1、Designation: C 1533 08Standard Guide forGeneral Design Considerations for Hot Cell Equipment1This standard is issued under the fixed designation C 1533; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revision. A n

2、umber 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 guide is to provide general designand operating considerations for the safe and dependableoperation of r

3、emotely operated hot cell equipment. Hot cellequipment is hardware used to handle, process, or analyzenuclear or radioactive material in a shielded room. Theequipment is placed behind radiation shield walls and cannotbe directly accessed by the operators or by maintenancepersonnel because of the rad

4、iation exposure hazards. There-fore, the equipment is operated remotely, either with or withoutthe aid of viewing.1.1.2 This guide may apply to equipment in other radioac-tive remotely operated facilities such as suited entry repairareas, canyons or caves, but does not apply to equipment usedin comm

5、ercial power reactors.1.1.3 This guide does not apply to equipment used ingloveboxes.1.2 Applicability:1.2.1 This guide is intended for persons who are tasked withthe planning, design, procurement, fabrication, installation, ortesting of equipment used in remote hot cell environments.1.2.2 The equip

6、ment will generally be used over a long-term life cycle (for example, in excess of two years), butequipment intended for use over a shorter life cycle is notexcluded.1.2.3 The system of units employed in this standard is themetric unit, also known as SI Units, which are commonly usedfor Internationa

7、l Systems, and defined by IEEE/ASTM SI 10:American National Standard for Use of the InternationalSystem of Units (SI): The Modern Metric System.1.3 Caveats:1.3.1 This guide does not address considerations relating tothe design, construction, operation, or safety of hot cells, caves,canyons, or other

8、 similar remote facilities. This guide dealsonly with equipment intended for use in hot cells.1.3.2 Specific design and operating considerations are foundin other ASTM documents.1.4 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is therespons

9、ibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory requirements prior to use.2. Referenced Documents2.1 ASTM Standards:2A 193/A 193M Specification for Alloy-Steel and StainlessSteel Bolting Materials for High Temp

10、erature or HighPressure Service and Other Special Purpose ApplicationsA 240/A 240M Specification for Chromium andChromium-Nickel Stainless Steel Plate, Sheet, and Stripfor Pressure Vessels and for General ApplicationsA 276 Specification for Stainless Steel Bars and ShapesA 320/A 320M Specification f

11、or Alloy-Steel and StainlessSteel Bolting Materials for Low-Temperature ServiceA 354 Specification for Quenched and Tempered AlloySteel Bolts, Studs, and Other Externally Threaded Fasten-ersA 479/A 479M Specification for Stainless Steel Bars andShapes for Use in Boilers and Other Pressure VesselsA 4

12、89 Specification for Carbon Steel Lifting EyesA 490 Specification for Structural Bolts, Alloy Steel, HeatTreated, 150 ksi Minimum Tensile StrengthC 859 Terminology Relating to Nuclear MaterialsC 1217 Guide for Design of Equipment for ProcessingNuclear and Radioactive MaterialsC 1554 Guide for Materi

13、als Handling Equipment for HotCellsC 1572 Guide for Dry Lead Glass and Oil-Filled Lead GlassRadiation Shielding Window Components for RemotelyOperated FacilitiesC 1615 Guide for Mechanical Drive Systems for RemoteOperation in Hot Cell FacilitiesC 1661 Guide for Viewing Systems for Remotely OperatedF

14、acilitiesD 676 Discontinued 1965; Method of Test for Indentationof Rubber by Means of a Durometer; Replaced by D 22403D 5144 Guide for Use of Protective Coating Standards in1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommitt

15、ee C26.14 on Remote Systems.Current edition approved Dec. 1, 2008. Published January 2009. Originallyapproved in 2002. Last previous edition approved in 2002 as C 1533 02.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Ann

16、ual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Withdrawn. The last approved version of this historical standard is referencedon www.astm.org.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-

17、2959, United States.Nuclear Power PlantsE 170 Terminology Relating to Radiation Measurementsand DosimetryF 593 Specification for Stainless Steel Bolts, Hex CapScrews, and StudsIEEE/ASTM SI 10 American National Standard for Use ofthe International System of Units (SI): The Modern MetricSystem2.2 Othe

18、r Standards:10CFR830.120 Nuclear Safety Management Quality As-surance Requirements4ANSI/ANS-8.1 Nuclear Criticality Safety in Operationswith Fissionable Materials Outside Reactors5ANSI/ASME NQA-1 Quality Assurance Requirements forNuclear Facility Applications6ANSI/ISO/ASQ 9001 Quality Management Sys

19、tems5ASME Y14.5 Dimensioning and Tolerancing6ICRU Report 10b Physical Aspects of Irradiation7NCRP Report No. 82 SI Units in radiation Protection andMeasurements83. Terminology3.1 The terminology employed in this guide conforms toindustry practice insofar as practicable.3.2 For definitions of terms n

20、ot described in this guide, referto Terminology C 859.3.3 Definitions of Terms Specific to This Standard:3.3.1 canyona long narrow, remotely operated and main-tained radiological area within a facility where nuclear materialis processed or stored.3.3.2 cavetypically a small-scale hot cell facility,

21、but issometimes used synonymously with hot cell.3.3.3 dose equivalentthe measure of radiation dose fromall types of radiation expressed on a common scale. Thespecialized unit for dose equivalent is the rem. The SI unit fordose equivalent is the sievert (Sv), which is equal to 100 rem.Human exposure

22、is often expressed in terms of microsieverts(SV), 1 3 106sieverts, or in terms of millirem (mrem),1 3103.3.3.4 electro-mechanical manipulator (E/M)usuallymounted on a crane bridge, wall, pedestal, or ceiling and isused to handle heavy equipment in a hot cell. Each joint of theE/M is operated by an e

23、lectric motor or electric actuator. TheE/M is operated remotely using controls from the uncontami-nated side of the hot cell. Most E/Ms have lifting capacities of100 lbs or more.3.3.5 gamma radiationhigh energy, short wavelengthelectromagnetic radiation which normally accompanies theother forms of p

24、article emissions during radioactive decay.Gamma radiation has no electrical charge.3.3.6 high density concretea concrete having a mass ofgreater than 2400 kg per cubic meter (150 lb per cubic foot).3.3.7 hot cellan isolated shielded room that provides acontrolled environment for containing highly r

25、adioactive andcontaminated material and equipment. The radiation levelswithin a hot cell are typically 1 Gy/hr (100 rads per hour) orhigher in air.3.3.8 master-slave manipulator (MSM)a device used tohandle items, tools, or radioactive material in a hot cell. Thein-cell or slave portion of the manipu

26、lator replicates the actionsof an operator outside of the hot cell by means of a through-wall mechanical connection between the two, usually withmetal tapes or cables. MSMs have lifting capacities of 9 to 23kg (20 to 50 lb).3.3.9 mock-upa facility used to represent the physicalenvironment of a radio

27、logical facility in a non-radiologicalsetting. Mock-ups are full scale facilities used to assure properclearances, accessibility, visibility, or operability of items to besubsequently installed in a radiological environment.3.3.10 radiation absorbed dose (rad)radiation absorbeddose is the quotient o

28、f the mean energy imparted by ionizingradiation to matter of mass. The SI unit for absorbed dose is thegray (NCRP Report No. 82).3.3.11 radiation streamingunshielded beams of radiation.3.3.12 roentgen equivalent man (rem)a measure of thedamaging effects of ionizing radiation to man. See doseequivale

29、nt (NCRP Report No. 82, ICRU Report 10b).4. Significance and Use4.1 The purpose of this guide is to provide general guide-lines for the design and operation of hot cell equipment toensure longevity and reliability throughout the period ofservice.4.2 It is intended that this guide record the general

30、condi-tions and practices that experience has shown is necessary tominimize equipment failures and maximize the effectivenessand utility of hot cell equipment. It is also intended to alertdesigners to those features that are highly desirable for theselection of equipment that has proven reliable in

31、high radia-tion environments.4.3 This guide is intended as a supplement to other stan-dards, and to federal and state regulations, codes, and criteriaapplicable to the design of equipment intended for hot cell use.4.4 This guide is intended to be generic and to apply to awide range of types and conf

32、igurations of hot cell equipment.5. Quality Assurance Requirements5.1 The manufacturer and Owner-Operator of hot cellequipment should have a quality assurance program. QAprograms may be required to comply with 10CFR830.120,ANSI/ASME NQA-1,orANSI/ISO/ASQ 9001.4Available from U.S. Government Printing

33、Office Superintendent of Documents,732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.5Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.6Available from American Society of Mechanical Engi

34、neers (ASME), ASMEInternational Headquarters, Three Park Ave., New York, NY 10016-5990, http:/www.asme.org.7Available from International Commission on Radiation Units and Measure-ments, Inc., 7910 Woodmont Ave., Suite 400, Bethesda, MD 20814-3095, http:/www.icru.org.8Available from National Council

35、of Radiation Protection and Measurements,7910 Woodmont Ave., Suite 400, Bethesda, MD 20814-3095, http:/www.ncrponline.org.C15330825.2 The Owner-Operator should require appropriate qualityassurance of purchased hot cell equipment to assure properremote installation, operation and reliability of the c

36、omponentswhen they are installed in the hot cell.5.3 Hot cell equipment should be designed according toquality assurance requirements and undergo quality controlinspections as outlined by the authority having jurisdiction.6. Nuclear Safety6.1 The handling and processing of special nuclear materi-als

37、 requires the avoidance of criticality incidents. Equipmentintended for use in handling materials having a special nuclearmaterial content should undergo a criticality assessment analy-sis in accordance with the requirements of ANSI/ANS-8.1 andother such standards and regulations as may be applicabl

38、e.7. Design Considerations7.1 Hot cell equipment should be designed and fabricated toremain dimensionally stable throughout its life cycle.7.2 Fabrication materials should be resistant to radiationdamage, or materials subject to such damage should beshielded or placed and attached so as to be readil

39、y replaceable.7.3 Special consideration should be given to designing hotcell equipment that may be exposed to or may create hightemperatures, high rate of temperature changes, caustic condi-tions, or pressure changes. Abrupt changes in the hot celltemperature or pressure may cause the hot cell windo

40、ws tocrack, lose clarity, and potentially lose containment and causeliquid spillage. Refer to Guide C 1572 for information regard-ing hot cell windows. The effect of handling and operating hightemperature hot cell equipment utilizing master-slave manipu-lators or other in-cell handling equipment sho

41、uld be consideredto preclude damage to those items.7.4 Preventive maintenance based on previous experience insimilar environments and similar duty should be performed asrequired to prevent unscheduled repair of failed components.7.5 Hot cell equipment may be required to be leak-tightwhen handling li

42、quids. Leak tightness prevents radioactiveliquid from entering the interior of hot cell equipment where itcan cause corrosion, shorting of electrical components, higherchronic radiation to components and it complicates decontami-nation.7.6 Hot cell equipment should generally be designed tofunction i

43、ndefinitely, or within a pre-planned specified lifecycle within the highly radioactive environment. However, inmany cases this may not be possible since radiation degradessome materials over time. Alpha, beta, gamma, and neutronradiation can severely damage most organic materials, forexample, oils,

44、plastics, and elastomers. Materials that comeinto direct contact with alpha- and beta-emitting materials canexperience severe radiation damage due to the large amount ofenergy transferred when stopping the alpha and beta particles.Commercially available equipment containing organic materi-als may re

45、quire disassembly and the internal componentsreplaced with more radiation resistant materials. If suitablealternate materials cannot be used, special shielding may haveto be integrated into the design to protect the degradablecomponents. In the case of some electronic equipment, it maybe possible to

46、 separate and move the more radiation sensitivecomponents outside of the hot cell and operate the equipmentin the hot cell remotely. Where possible and appropriate,equipment should be designed to withstand an accumulativeradiation dose of approximately 1 3 108rads (H2O)60Co.7.7 Since hot cells have

47、a limited amount of space, theequipment designs should be standardized where possible toreduce the number of one-of-a-kind parts. Standardization ofhot cell equipment will reduce design time, fabrication costs,operator training time, maintenance costs, and the number ofspecial tools required to perf

48、orm a certain operation. Standard-ization in design, drawing control and excellent quality controlassure that components are interchangeable. Specially de-signed equipment should be standardized for use with equip-ment in similar applications or systems to reduce spare partsinventories and to mainta

49、in familiarity for the operators.Commercially available components should be used, andmodified if necessary, wherever possible in preference tospecially designed equipment.7.8 All hot cell equipment should be designed in modulesfor ease of replacement, maintainability, interchangeability,standardization, and ease of disposal. The modules should bedesigned to be remotely removable and installed using thein-cell handling equipment, that is, master-slave manipulators,cranes, etc. Consideration should also be given to the transferpath to get equipment into the hot c