1、Designation: C1533 08C1533 15Standard Guide forGeneral Design Considerations for Hot Cell Equipment1This standard is issued under the fixed designation C1533; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revisio
2、n. 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 guide is to provide general design and operating considerations for the safe and dependable operat
3、ionof remotely operated hot cell equipment. Hot cell equipment is hardware used to handle, process, or analyze nuclear or radioactivematerial in a shielded room. The equipment is placed behind radiation shield walls and cannot be directly accessed by the operatorsor by maintenance personnel because
4、of the radiation exposure hazards. Therefore, the equipment is operated remotely, either withor without the aid of viewing.1.1.2 This guide may apply to equipment in other radioactive remotely operated facilities such as suited entry repair areas,canyons or caves, but does not apply to equipment use
5、d in commercial power reactors.1.1.3 This guide does not apply to equipment used in gloveboxes.1.2 Applicability:1.2.1 This guide is intended for persons who are tasked with the planning, design, procurement, fabrication, installation, ortesting of equipment used in remote hot cell environments.1.2.
6、2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipmentintended for use over a shorter life cycle is not excluded.1.2.3 The system of units employed in this standard is the metric unit, also known as SI Units, which are commonly used fo
7、rInternational Systems, and defined by IEEE/ASTM SI 10:American National Standard for Use of the International System of Units(SI): The Modern Metric System.1.3 Caveats:1.3.1 This guide does not address considerations relating to the design, construction, operation, or safety of hot cells, caves,can
8、yons, or other similar remote facilities. This guide deals only with equipment intended for use in hot cells.1.3.2 Specific design and operating considerations are found in other ASTM documents.1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use.
9、 It is the responsibilityof the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatoryrequirements prior to use.2. Referenced Documents2.1 ASTM Standards:2A193/A193M Specification forAlloy-Steel and Stainless Steel Bolting for HighTem
10、perature or High Pressure Service and OtherSpecial Purpose ApplicationsA240/A240M Specification for Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for Pressure Vessels andfor General ApplicationsA276 Specification for Stainless Steel Bars and ShapesA320/A320M Specification for
11、Alloy-Steel and Stainless Steel Bolting for Low-Temperature ServiceA354 Specification for Quenched and Tempered Alloy Steel Bolts, Studs, and Other Externally Threaded FastenersA479/A479M Specification for Stainless Steel Bars and Shapes for Use in Boilers and Other Pressure VesselsA489 Specificatio
12、n for Carbon Steel Lifting EyesA490 Specification for Structural Bolts, Alloy Steel, Heat Treated, 150 ksi Minimum Tensile Strength1 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 edit
13、ion approved Dec. 1, 2008Jan. 1, 2015. Published January 2009February 2015. Originally approved in 2002. Last previous edition approved in 20022008 asC1533 02.C1533 08. DOI: 10.1520/C1533-08.10.1520/C1533-15.2 For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer
14、 Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.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 pr
15、evious 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 by ASTM is to be considered the official document.Copyright ASTM
16、International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1C859 Terminology Relating to Nuclear MaterialsC1217 Guide for Design of Equipment for Processing Nuclear and Radioactive MaterialsC1554 Guide for Materials Handling Equipment for Hot CellsC1572 Guide f
17、or Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely OperatedFacilitiesC1615 Guide for Mechanical Drive Systems for Remote Operation in Hot Cell FacilitiesC1661 Guide for Viewing Systems for Remotely Operated FacilitiesC1725 Guide for Hot Cell Specialized Su
18、pport Equipment and ToolsD676 Method of Test for Indentation of Rubber by Means of a Durometer; Replaced by D 2240 (Withdrawn 1964)3D5144 Guide for Use of Protective Coating Standards in Nuclear Power PlantsE170 Terminology Relating to Radiation Measurements and DosimetryF593 Specification for Stain
19、less Steel Bolts, Hex Cap Screws, and StudsIEEE/ASTM SI 10 American National Standard for Use of the International System of Units (SI): The Modern Metric System2.2 Other Standards:10CFR830.120 Nuclear Safety Management Quality Assurance Requirements4ANSI/ANS-8.1 Nuclear Criticality Safety in Operat
20、ions with Fissionable Materials Outside Reactors5ANSI/ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications6ANSI/ISO/ASQ 9001 Quality Management Systems5ASME Y14.5 Dimensioning and Tolerancing6ICRU Report 10b Physical Aspects of Irradiation7NCRP Report No. 82 SI Units in radiat
21、ion Protection and Measurements83. Terminology3.1 The terminology employed in this guide conforms to industry practice insofar as practicable.3.2 For definitions of terms not described in this guide, refer to Terminology C859.3.3 Definitions of Terms Specific to This Standard:3.3.1 canyona long narr
22、ow, remotely operated and maintained radiological area within a facility where nuclear material isprocessed or stored.3.3.2 cavetypically a small-scale hot cell facility, but is sometimes used synonymously with hot cell.3.3.3 dose equivalentthe measure of radiation dose from all types of radiation e
23、xpressed on a common scale. The specializedunit for dose equivalent is the rem. The SI unit for dose equivalent is the sievert (Sv), which is equal to 100 rem. Human exposureis often expressed in terms of microsieverts (SV),(Sv), 1 106 sieverts, or in terms of millirem (mrem),1 103.3.3.4 electro-mec
24、hanical manipulator (E/M)usually mounted on a crane bridge, wall, pedestal, or ceiling and is used to handleheavy equipment in a hot cell. Each joint of the E/M is operated by an electric motor or electric actuator. The E/M is operatedremotely using controls from the uncontaminated side of the hot c
25、ell. Most E/Ms have lifting capacities of 100 lbs or more.3.3.5 gamma radiationhigh energy, short wavelength electromagnetic radiation which normally accompanies the other formsof particle emissions during radioactive decay. Gamma radiation has no electrical charge.3.3.6 high density concretea concr
26、ete having a massdensity of greater than 2400 kgkg/m3 per cubic meter (150 lb (150lb/ft3per cubic foot).).3.3.7 hot cellan isolated shielded room that provides a controlled environment for containing highly radioactive andcontaminated material and equipment. The radiation levels within a hot cell ar
27、e typically 1 Gy/hrGy/h (100 rads per hour) or higherin air.3.3.8 master-slave manipulator (MSM)a device used to handle items, tools, or radioactive material in a hot cell. The in-cellor slave portion of the manipulator replicates the actions of an operator outside of the hot cell by means of a thro
28、ugh-wallmechanical connection between the two, usually with metal tapes or cables. MSMs have lifting capacities of 9 to 23 kg (20 to 50lb).3 The last approved version of this historical standard is referenced on www.astm.org.4 Available from U.S. Government Printing Office Superintendent of Document
29、s, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.5 Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http:/www.ansi.org.6 Available from American Society of Mechanical Engineers (ASME), ASME Internatio
30、nal Headquarters, ThreeTwo Park Ave., New York, NY 10016-5990,http:/www.asme.org.7 Available from International Commission on Radiation Units and Measurements, Inc., 7910 WoodmontAve., Suite 400, Bethesda, MD 20814-3095, http:/www.icru.org.8 Available from National Council of Radiation Protection an
31、d Measurements, 7910 Woodmont Ave., Suite 400, Bethesda, MD 20814-3095, http:/www.ncrponline.org.C1533 1523.3.9 mock-upa facility used to represent the physical environment of a radiological facility in a non-radiological setting.Mock-ups are full scale facilities used to assure proper clearances, a
32、ccessibility, visibility, or operability of items to be subsequentlyinstalled in a radiological environment.3.3.10 radiation absorbed dose (rad)radiation absorbed dose is the quotient of the mean energy imparted by ionizing radiationto matter of mass. The SI unit for absorbed dose is the gray (NCRP
33、Report No. 82).3.3.11 radiation streamingunshielded beams of radiation.3.3.12 roentgen equivalent man (rem)a measure of the damaging effects of ionizing radiation to man. See dose equivalent(NCRP Report No. 82, ICRU Report 10b).4. Significance and Use4.1 The purpose of this guide is to provide gener
34、al guidelines for the design and operation of hot cell equipment to ensurelongevity and reliability throughout the period of service.4.2 It is intended that this guide record the general conditions and practices that experience has shown is necessary to minimizeequipment failures and maximize the ef
35、fectiveness and utility of hot cell equipment. It is also intended to alert designers to thosefeatures that are highly desirable for the selection of equipment that has proven reliable in high radiation environments.4.3 This guide is intended as a supplement to other standards, and to federal and st
36、ate regulations, codes, and criteria applicableto the design of equipment intended for hot cell use.4.4 This guide is intended to be generic and to apply to a wide range of types and configurations of hot cell equipment.5. Quality Assurance Requirements5.1 The manufacturer and Owner-Operator of hot
37、cell equipment should have a quality assurance program. QA programs maybe required to comply with 10CFR830.120, ANSI/ASME NQA-1, or ANSI/ISO/ASQ 9001.5.2 The Owner-Operator should require appropriate quality assurance of purchased hot cell equipment to assure proper remoteinstallation, operation and
38、 reliability of the components when they are installed in the hot cell.5.3 Hot cell equipment should be designed according to quality assurance requirements and undergo quality control inspectionsas outlined by the authority having jurisdiction.6. Nuclear Safety6.1 The handling and processing of spe
39、cial nuclear materials requires the avoidance of criticality incidents. Equipment intendedfor use in handling materials having a special nuclear material content should undergo a criticality assessment analysis inaccordance with the requirements of ANSI/ANS-8.1 and other such standards and regulatio
40、ns as may be applicable.7. Design Considerations7.1 Hot cell equipment should be designed and fabricated to remain dimensionally stable throughout its life cycle.7.2 Fabrication materials should be resistant to radiation damage, or materials subject to such damage should be shielded orplaced and att
41、ached so as to be readily replaceable.7.3 Special consideration should be given to designing hot cell equipment that may be exposed to or may create hightemperatures, high rate of temperature changes, caustic conditions, or pressure changes.Abrupt changes in the hot cell temperatureor pressure may c
42、ause the hot cell windows to crack, lose clarity, and potentially lose containment and cause liquid spillage. Referto Guide C1572 for information regarding hot cell windows. The effect of handling and operating high temperature hot cellequipment utilizing master-slave manipulators or other in-cell h
43、andling equipment should be considered to preclude damage tothose items.7.4 Preventive maintenance based on previous experience in similar 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
44、-tight when handling liquids. Leak tightness prevents radioactive liquid fromentering the interior of hot cell equipment where it can cause corrosion, shorting of electrical components, higher chronic radiationto components and it complicates decontamination.7.6 Hot cell equipment should generally b
45、e designed to function indefinitely, or within a pre-planned specified life cycle withinthe highly radioactive environment. However, in many cases this may not be possible since radiation degrades some materials overtime. Alpha, beta, gamma, and neutron radiation can severely damage most organic mat
46、erials, for example, oils, plastics, andelastomers. Materials that come into direct contact with alpha- and beta-emitting materials can experience severe radiation damagedue to the large amount of energy transferred when stopping the alpha and beta particles. Commercially available equipmentcontaini
47、ng organic materials may require disassembly and the internal components replaced with more radiation resistant materials.If suitable alternate materials cannot be used, special shielding may have to be integrated into the design to protect the degradableC1533 153components. In the case of some elec
48、tronic equipment, it may be possible to separate and move the more radiation sensitivecomponents outside of the hot cell and operate the equipment in the hot cell remotely. Where possible and appropriate, equipmentshould be designed to withstand an accumulative radiation dose of approximately 1 108
49、rads (H2O)60Co.7.7 Since hot cells have a limited amount of space, the equipment designs should be standardized where possible to reduce thenumber of one-of-a-kind parts. Standardization of hot cell equipment will reduce design time, fabrication costs, operator trainingtime, maintenance costs, and the number of special tools required to perform a certain operation. Standardization in design,drawing control and excellent quality control assure that components are interchangeable. Specially designed equipment shouldbe standardized for use with equipm
