1、Designation: C 1217 00 (Reapproved 2006)Standard Guide forDesign of Equipment for Processing Nuclear andRadioactive Materials1This standard is issued under the fixed designation C 1217; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revisio
2、n, the year of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) indicates an editorial change since the last revision or reapproval.1. Scope1.1 Intent:1.1.1 This guide covers equipment used in shielded cell orcanyon facilities for the processing
3、of nuclear and radioactivematerials. It is the intent of this guide to set down theconditions and practices that have been found necessary toensure against or to minimize the failures and outages ofequipment used under the subject circumstances.1.1.2 It is intended that this guide record the princip
4、les andcaveats that experience has shown to be essential to the design,fabrication, and installation of equipment capable of meetingthe stringent demands of operating, dependably and safely, ina nuclear processing environment that operators can neither seenor reach directly.1.1.3 This guide sets for
5、th generalized criteria and guide-lines for the design, fabrication, and installation of equipmentused in this service. This service includes the processing ofradioactive wastes. Equipment is placed behind radiationshield walls and cannot be directly accessed by the operators orby maintenance person
6、nel because of the radiation exposurehazards. In the type of shielded cell or canyon facility ofinterest to users of this guide, either the background radiationlevel remains high at all times or it is impractical to remove theprocess sources of radiation to facilitate in situ repairs or carryout mai
7、ntenance procedures on equipment. The equipment isoperated remotely, either with or without visual access to theequipment.1.2 Applicability:1.2.1 This guide is intended to be applicable to equipmentused under one or more of the following conditions:1.2.1.1 The materials handled or processed constitu
8、te asignificant radiation hazard to man or to the environment.1.2.1.2 The equipment 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.1.2.1.3 The material handled or processed must be retai
9、ned,contained, and confined within known bounds for reasons ofaccountability or to minimize the spread of radioactive con-tamination.1.2.1.4 The materials handled or processed must be kept andmaintained within one or more of the following conditions:(1) In a specific geometric array or configuration
10、, and(2) Within a range of conditions that have been determinedto be a critically safe set of conditions for that piece ofequipment, that is, 1) in a given and specified operationalposition where adjacent nuclear criticality interaction condi-tions are known and unchanging, 2) for a given and specif
11、iedset or range of operating conditions, and 3) for a given andspecified process.1.2.1.5 The equipment can neither be accessed directly forpurposes of operation or maintenance, nor can the equipmentbe viewed directly, for example, without intervening shieldedviewing windows, periscopes, or a televis
12、ion monitoring sys-tem.1.2.2 This guide is intended to be applicable to the design ofequipment for the processing of materials containing uraniumand transuranium elements in any physical form under thefollowing conditions:1.2.2.1 Such materials constitute an unacceptable radiationhazard to the opera
13、tors and maintenance personnel,1.2.2.2 The need exists for the confinement of the in-processmaterial, of dusts and particulates, or of vapors and gasesarising or resulting from the handling and processing of suchmaterials, and1.2.2.3 Any of the conditions cited in 1.2.1 apply.1.2.3 This guide is int
14、ended to apply to the design, fabrica-tion, and installation of ancillary and support services equip-ment under the following conditions:1.2.3.1 Such equipment is installed in shielded cell orcanyon environments, or1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and
15、is the direct responsibility of Subcommittee C26.09 on NuclearProcessing.Current edition approved Jan. 1, 2006. Published February 2006 . Originallyapproved in 1992. Last previous edition approved in 2000 as C 121700.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocke
16、n, PA 19428-2959, United States.1.2.3.2 Such equipment is an integral part of an in-cellprocessing equipment configuration, or an auxiliary componentor system thereof, even though an equipment item or systemmay not directly hold or contain nuclear or radioactive mate-rials under normal processing co
17、nditions.NOTE 1Upsets, accidents, or certain emergency conditions may bespecified (and thus required) design considerations, but not necessarilyacceptable or normal operating circumstances under this definition.1.2.4 This guide is intended to apply to the design andfabrication of any and all types o
18、f equipment for radioactivewastes processing when any of the conditions cited in 1.2.1apply. This would include equipment for waste concentration;for incorporation of wastes in selected host materials ormatrices; and for the fixation, encapsulation, or canning of suchwastes. It is intended to apply
19、to all such wastes, regardless ofthe product waste composition or form. The product radioac-tive waste may have a glass, ceramic, metallic, concrete,bituminous, or other type of host material or matrices (com-position), and may be in pelletized, solid, or granular form.1.3 User Caveats:1.3.1 This st
20、andard 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 limitations prior to use.NOTE 2Warning: This standa
21、rd pertains to equipment used in and forthe handling and processing of nuclear and radioactive materials. Theseoperations are known to be hazardous for a variety of reasons, one beingchemical toxicity.1.3.2 This standard is not a substitute for applied engineer-ing skills. Its purpose is to provide
22、guidance.1.3.2.1 The guidance set forth in this standard relating todesign of equipment is intended only to alert designers andengineers to those features, conditions, and procedures thathave been found necessary or highly desirable to the acquisi-tion of reliable equipment for the subject service c
23、onditions.1.3.2.2 The guidance set forth results from discoveries ofconditions, practices, features, or lack of features that werefound to be sources of operational or maintenance trouble, orcauses of failure.1.3.3 It is often necessary to maintain the materials beingprocessed within specific chemic
24、al composition or concentra-tion ranges, or both. When such constraints apply, it may alsobe necessary to create and maintain a specific geometric arrayto minimize the chances of a nuclear criticality incident.Designers and engineers are referred to other standards foradditional guidance when such r
25、equirements apply.1.3.4 Equipment usage intent, service conditions, size andconfiguration, plus the configuration and features of the oper-ating and maintenance environments have an influence onequipment design. Therefore, not all of the criteria, conditions,caveats, or features would be applicable
26、to every equipmentitem.1.3.5 It is intended that equipment designed, fabricated,procured, or obtained by transfer or adaptation and re-use ofexisting equipment, and installed in accord with the standardmeet or exceed statutory, regulatory, and safety requirementsfor that equipment under the applicab
27、le operating and serviceconditions.1.3.6 This standard does not supersede federal or stateregulations, or both, and codes applicable to equipment underany conditions.2. Referenced Documents2.1 Industry and National Consensus StandardsNationally recognized industry and consensus standards appli-cable
28、 in whole or in part to the design, fabrication, andinstallation of equipment are referenced throughout this guideand include the following:2.2 ASTM Standards:2C 859 Terminology Relating to Nuclear Materials3D 5144 Guide for Use of Protective Coating Standards inNuclear Power Plants2.3 ANSI Standard
29、s:4ANSI/ANS 8.1 Nuclear Criticality Safety in Operationswith Fissile Materials Outside ReactorsANS Glossary of Terms in Nuclear Science and Technol-ogy (ANS Glossary)ANSI A14.3 Ladders, Fixed Safety Requirements2.4 ASME Standard:5Boiler and Pressure Vessel Code, Section VIIIASME NQA1 QualityAssuranc
30、e Requirements for NuclearFacility ApplicationsASME NOG-1, Rules for Construction of Overhead GantryCranes (Top-Running Bridge, Multiple Girder)2.5 Federal Regulations:610CFR50, Appendix B, Quality Assurance29CFR1910, Occupational Safety and Health Standards2.6 National Electrical Manufacturers Asso
31、ciation (NEMA)Standards:7NEMA 250 Enclosures for Electrical Equipment 1000 VoltsMaximum (Type 4)2.7 National Fire Protection Association (NFPA) Stan-dards:8NFPA 70, National Electric Code3. Terminology3.1 Definitions:3.1.1 The terminology employed in this guide conformswith industry practice insofar
32、 as practicable.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Withdrawn.4Available from American National
33、Standards Institute, 11 W. 42ndSt., 13thFl.,New York, NY 10036.5Available from American Society of Mechanical Engineers, 3 Park Ave., NewYork, NY 10016.6Available from U.S. Government Printing Office, Superintendent of Docu-ments, Mail Stop SSOP, Washington, DC 20402-9328.7Available from Global Engi
34、neering Co., 15 Inverness Way, Englewood, CO80112.8Available from National Fire Protection Agency (NFPA), One BatterymarchPark, Quincy, MA 02269.C 1217 00 (2006)23.1.2 For definitions of terms used in this guide, refer toTerminology C 859 and ANS Glossary.3.2 Descriptions of Terms Specific to This S
35、tandardTheterms defined below are of a restricted nature, specificallyapplicable to this guide.3.2.1 accidentan unplanned event that could result inunacceptable levels of any of the following: (1) equipmentdamage, (2) injury to personnel, (3) downtime or outage, (4)release of hazardous materials (ra
36、dioactive or non-radioactive),(5) radiation exposure to personnel, or (6) criticality.3.2.2 accountabilitythe keeping of detailed records on,and the responsibilityon the part of operations personnel andplant managementof being accountable for the amounts ofspecial nuclear materials entering and leav
37、ing a plant, a vessel,or a defined processing step.3.2.3 datum connection pointsthose locations on equip-ment where separate auxiliary equipment items such as pumps,agitators, columns, condensers, and other separately removableequipment pieces are mounted, or where process, service,instrumentation,
38、or electrical jumper connections are made.3.2.3.1 DiscussionThese datum connection points are po-sitioned by dimensioning from (theoretically) perfectly placedbase X, Y and Z datum planes; for example, such points orlocations are dimensionally located by three-plane coordinatedimensions. Datum conne
39、ction points are the loci of position-ing elements such as dowels, trunnions, trunnion guides, andsuch other devices or elements that serve to align, position, orlocate equipment in a precise position or array, or which serveas a point for the connection or placement of other compo-nents.3.2.4 engin
40、eering responsibilityan obligation to performengineering design activities assigned to a specified organiza-tion.3.2.5 geometrically favorableequipment having set di-mensions, and a shape or a layout configuration, that providesassurance that a criticality incident cannot occur in the equip-ment or
41、system under a given set of circumstances or condi-tions.3.2.5.1 DiscussionThe given set of conditions or circum-stances requires that the isotopic composition, form, concen-tration, and density of fissile materials in the equipment orsystem will not violate those assumed and used for thepreparation
42、 of the criticality analysis, and that those variableswill remain within conservatively chosen limits, and thatnuclear criticality interaction conditions will be within somepermitted, pre-set range.3.2.6 jumpersthe pipe line, electrical service, or instru-mentation service connector assemblies that
43、span the gapbetween nozzles or connection points on the canyon orcell-mounted equipment and (1) nozzles or connection pointson adjacent or nearby vessels, or (2) service nozzles orconnector points on the interior sides of the cell or shield walls.3.2.7 owner-operatorthe firm having either legal owne
44、r-ship responsibilities and rights for the nuclear and radioactivematerials handling/processing facility where subject equipmentis to be installed and/or used, or the firm that has accepted allmanagement, engineering, operation, and maintenance respon-sibilities and rights (or specified portions the
45、reof) by way ofcontractual arrangement(s) with the legal owner of the facili-ties.4. Significance and Use4.1 Equipment operability and long-term integrity are con-cerns that originate during the design and fabrication se-quences. Such concerns can only be addressed or are mostefficiently addressed d
46、uring one or the other of these stages.Equipment operability and integrity can be compromisedduring handling and installation sequences. For this reason, thesubject equipment should be handled and installed underclosely controlled and supervised conditions.4.2 This guide is intended as a supplement
47、to other stan-dards, and to federal and state regulations, codes, and criteriaapplicable to the design of equipment intended for this use.4.3 This guide is intended to be generic and to apply to awide range of equipment types and configurations.4.4 The term equipment is used herein in a generic sens
48、e.See 3.2.5 for the definition.4.5 This service imposes stringent requirements on thequality and the integrity of the equipment, as follows:4.5.1 Leak tightness is required. This implies containmentof liquids at all times, and retention of vapors and gases bymeans of vessel design, or through means
49、of engineeredprovisions or operational procedures, or both, that ensure theretention, collection, and treatment of vapors and off-gaseswhen the vessel cannot be fabricated or operated with anair-tight vessel configuration. Radioactive materials must becontained.4.5.2 Equipment must be capable of withstanding rigorouschemical cleaning and decontamination procedures.4.5.3 Equipment must be designed and fabricated to remaindimensionally stable throughout its life cycle.4.5.4 Close fabrication tolerances are required to set nozzlesand other datum points in known positions.
