ASTM E2216-2002 Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning《核设施退役区混凝土处理方案的评估标准指南》.pdf

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1、Designation: E 2216 02Standard Guide forEvaluating Disposal Options for Concrete from NuclearFacility Decommissioning1This standard is issued under the fixed designation E 2216; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the y

2、ear 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.INTRODUCTIONNumerous nuclear facilities containing large amounts of concrete are scheduled for decontaminationand decommis

3、sioning over the next several decades. Much of this concrete is either not contaminatedor only lightly contaminated on or near the surface. However, since concrete is slightly porous, it hasthe potential to be contaminated volumetrically. Volumetric contamination is more difficult to measurethan sur

4、face contamination, and currently there are no release guidelines for volumetricallycontaminated concrete. As a result, large volumes of concrete are often disposed of as radioactivewaste at a large cost.Under certain conditions, the depth or amount of contamination may be limited such that a case c

5、anbe made for concrete release for other purposes outside of regulatory control. These cases are likelyto be ones where the radioactive contamination is shallow and is limited to a depth that can beremoved by scabbling (removal of the concrete surface), or where the depth can be estimated basedon th

6、e history and condition of the concrete. In addition to surface contaminated concrete, somefacilities contain activated concrete where the depths of contamination vary. This type of concreteshould be handled on a case-by-case basis. Accurate measurements of the radiation source are difficultfor acti

7、vated concrete, because the activated portions of the embedded metal or concrete are partiallyshielded by the concrete that lies between the source and the measuring device. Care must be takento measure radiation levels of activated concrete accurately, so actual radiation levels are documentedand u

8、sed when applying release criteria.This standard guide applies to nonrubbelized concrete that is still in place with a defined geometryand known history where the depth of contamination can be measured or estimated based on itshistory. It is not practical to measure radiation levels of concrete rubb

9、le. The process outlined herestarts with characterizing the concrete in place, then evaluating the dose to the public and cost ofvarious disposal options.1. Scope1.1 This standard guide defines the process for developing astrategy for dispositioning concrete from nuclear facility de-commissioning. I

10、t outlines a 10-step method to evaluatedisposal options for radioactively contaminated concrete. Oneof the steps is to complete a detailed analysis of the cost anddose to nonradiation workers (the public); the methodologyand supporting data to perform this analysis are detailed in theappendices. The

11、 resulting data can be used to balance dose andcost and select the best disposal option. These data, whichestablish a technical basis to apply to release the concrete, canbe used in several ways: (1) to show that the release meetsexisting release criteria, (2) to establish a basis to requestrelease

12、of the concrete on a case-by-case basis, (3) to developa basis for establishing release criteria where none exists.1.2 This standard guide is based on the “Protocol forDevelopment of Authorized Release Limits for Concrete atU.S. Department of Energy Sites,” (Arnish, J. et.al., 2000)from which the an

13、alysis methodology and supporting data aretaken.1.3 Guide E 1760 provides a general process for release ofmaterials containing residual amounts of radioactivity. Inaddition, Guide E 1278 provides a general process for analyz-ing radioactive pathways. This standard guide is intended for1This guide is

14、 under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.03 on Radiological Protection for Decontamination and Decommissioning ofNuclear Facilities and Components.Current edition approved June 10, 2002. Published October

15、2002.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.use in conjunction with Guides E 1760 and E 1278, andprovides a more detailed approach for the release of concrete.2. Referenced Documents2.1 ASTM Standards:E 1278 Guide for Radioa

16、ctive Pathway Methodology forRelease of Sites Following Decommissioning2E 1760 Guide for Unrestricted Disposition of Bulk Materi-als Containing Residual Amounts of Radioactivity2E 1893 Guide for Selection and Use of Portable Radiologi-cal Survey Instruments for Performing In Situ RadiologicalAssessm

17、ents in Support of Decommissioning22.2 ANSI Standards:3ANSI/USAS N13.12 Surface and Volume RadioactivityStandards for ClearanceANSI/USAS N13.2 Guide for Administrative Practices inRadiation Monitoring2.3 IAEA Standards:4Safety Series No. 111-P-1.1 Application of Exemption Prin-ciples to the Recycle

18、and Reuse of Materials from NuclearFacilitiesIAEA-TECDOC-855 Clearance Levels for Radionuclidesin Solid Materials, (Interim Report for Comment)2.4 ISO Standards:5ISO-4037 X and Gamma Reference Radiations for Calibrat-ing Dosimeters and Dose-rate Meters and for Determiningtheir Response as a Function

19、 of Photon EnergyISO-6980 Reference Beta Radiations for Calibrating Do-simeters and Dose-rate Meters and for Determining TheirResponse as a Function of Beta Radiation EnergyISO-8769 Reference Sources for the Calibration of SurfaceContamination MonitorsBeta Emitters (Maximum BetaEnergy Greater than 0

20、.15 MeV) and Alpha EmittersISO-7503-1 Evaluation of Surface ContaminationPart 1:Beta Emitters (Maximum Beta Energy Greater than 0.15MeV) and Alpha EmittersISO-7503-2 Evaluation of Surface ContaminationPart 2:Tritium Surface ContaminationISO-7503-3 Evaluation of Surface ContaminationPart 3:Isomeric T

21、ransition and Electron Capture Emitters, LowEnergy Beta Emitters (EBmax0.15 MeV)2.5 DOE Standards:6DOE G 4441.17 Portable Monitoring Instrument Calibra-tion Guide for Use With Title 10, Code of FederalRegulations, Part 835, Occupational Radiation Program,6171999.Order 5400.5 Radiation Protection of

22、the Public and theEnvironment, as amended2.6 U.S. Government Documents:7NUREG-1640 Radiological Assessments for Clearance ofEquipment and Materials From Nuclear FacilitiesNUREG/CR-5512 Residual Radioactive ContaminationFrom Decommissioning10 CFR 20 Standards for Protection Against Radiation2.7 NRC S

23、tandards:8Regulatory Guide 1.86 Termination of Operating Licensesfor Nuclear Reactors3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 activated concreteconcrete that has components(such as metal filings or pieces) that have become radioactivethrough exposure to high radiation f

24、ields; the concrete itself isradioactive.3.1.2 as low as reasonably achievable (ALARA)is a pro-cess used for radiation protection to manage and controlexposures (both individual and collective to the work force andto the general public) and releases of radioactive material to theenvironment so that

25、the levels are as low as is reasonabletaking into account social, technical, economic, practical, andpublic policy consideration. ANSI/HPS N13.123.1.3 releaseoccurs when property is transferred out ofregulatory control by sale, lease, gift, or other disposition,provided that the property does not re

26、main under radiologicalcontrol by a regulatory agency. The release does not apply toreal property (such as real estate), radioactive wastes, soils,liquid discharges, or gaseous or radon emissions.3.1.4 surface contaminationradioactive contamination re-siding on or near the surface of an item. This c

27、ontamination canbe adequately quantified in terms of activity per unit area.ANSI/HPS N13.123.1.5 volumetric contaminationradioactive contaminationresiding in or throughout the volume of an item. Volumetriccontamination can result from neutron activation or from thepenetration of radioactive contamin

28、ation into cracks or interiorsurfaces within the interior matrix of an item. ANSI/HPSN13.124. Significance and Use4.1 This standard guide applies to concrete that is still inplace with a defined geometry and known, documented history.4.2 It is not intended for use on concrete that has alreadybeen ru

29、bbelized where it is difficult to measure the radiationlevels and not easy to remove surface contamination to reduceradiation levels after concrete has been rubbelized.4.3 This standard guide applies to surface or volumetricallycontaminated concrete, where the depth of contamination canbe measured o

30、r estimated based on the history of the concrete.4.4 This standard guide does not apply to the reinforcementbar (rebar) found in concrete. Although most concrete contains2Annual Book of ASTM Standards, Vol 12.02.3Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor,

31、New York, NY 10036.4Available from International Atomic Energy Agency, Wagramerstrasse, PO Box100 A-1400, Vienna, Austria.5Available from International Organization for Standardization (ISO), 1 rue deVaremb, Case postale 56, CH-1211, Geneva 20, Switzerland.6Available from United States Department of

32、 Energy, National TechnicalInformation Service, US Dept. of Commerce, Springfield, VA 22161.7Available from the Superintendent of Documents, US Government PrintingOffice, Washington, DC 20402.8Available from Nuclear Regulatory Commission, Public Document Room,1717H St. NW, Washington, DC 20555.E2216

33、022rebar, it is generally removed before the concrete is disposi-tioned. In addition, rebar may be activated, and is coveredunder procedures for reuse of scrap metal.4.5 General unit-dose and unit-cost data to support thecalculations is provided in the appendices of this standardguide. However, if s

34、ite-specific data is available, it should beused instead of the general information provided here.4.6 This standard guide helps determine estimated doses tothe public during disposal of concrete and to future residents ofdisposal areas. It does not include dose to radiation workersalready involved i

35、n a radiation control program. It is assumedthat the dose to radiation workers is already tracked and keptwithin acceptable levels through a radiation control program.The cost and dose to radiation workers could be added in tofind an overall cost and dose for each option.5. Elements of the Release P

36、rocess5.1 This standard guide describes the steps of an overallrelease process for radioactively contaminated concrete fromdecommissioning nuclear facilities. As one of the steps, itprovides a method and supporting data to estimate the dose andcost impacts for various disposal options. This data can

37、 be usedto select the best disposal option, which should be one thatmeets regulatory guidelines while reducing dose and cost.Release of any surface or volumetrically contaminated materialmust meet all criteria of the governing regulatory agencies.5.2 S.Y. Chen, et al, (1999), described a 10-step rel

38、easeprocess in the publication, “Authorized Release of DOEsNon-Real Property: Process and Approach.” These 10 steps arethe basis for the, “Protocol for Development of AuthorizedRelease Limits for Concrete at U.S. Department of EnergySites” (Arnish, J., et al, 2000) and also for this standard guide.5

39、.2.1 Characterize property and prepare a description;5.2.2 Determine whether applicable authorized or supple-mental guidelines already exist;5.2.3 Define authorized or supplemental guidelines needed;5.2.4 Develop authorized or supplemental guidelines;5.2.5 Compile and submit application for approval

40、 from theregulatory agencies;5.2.6 Document approved guidelines in the public record;5.2.7 Implement approved guidelines;5.2.8 Conduct surveys/measurements;5.2.9 Verify that applicable authorized or supplementalguidelines have been met; and5.2.10 Release property.5.3 Characterize Property and Prepar

41、e a Description:5.3.1 Document the concretes physical and radiologicalcharacteristics, including history. The concretes history andcondition can be used to estimate the depth of penetration ofradioactive contamination, or this can be measured. Radiologi-cal surveys must be done to determine the isot

42、opes and level ofradioactive contamination on the surface of the concrete.5.4 Determine Whether Authorized Release Guidelines Al-ready Exist:5.4.1 If surface or volumetric activity release guidelinesexist, and the concrete is below those levels, the concrete canbe released through approved regulator

43、y methods. Documentsincluding ANSI/HPS N13.12-1999, U.S. NRC RegulatoryGuide 1.86, and others may provide applicable release guide-lines. In any case, this standard guide can be used to completean analysis of the dose and cost for various disposal optionsand select the best one. All required regulat

44、ory approvals muststill be obtained before releasing the concrete.5.4.2 If no existing guidelines apply, this standard guide canbe used to estimate the ramifications of each disposal option,select the best disposal option, and then apply for approval torelease the material based on these data. Such

45、releases could bedone on a case-by-case basis, or to set a new authorized releaselimit.5.5 Define What Authorized or Supplemental Guidelines areNeeded:5.5.1 If authorized release guidelines do not exist, definewhat type of guidelines need to be developed:5.5.1.1 Surface or volumetric contamination;5

46、.5.1.2 One-time or routine release;5.5.1.3 Restricted or unrestricted release.5.6 Define Authorized or Supplemental Guidelines:5.6.1 Estimate the dose and cost for the various disposaloptions. Each disposal option consists of a set of actions suchas decontamination and disposal. The dose and cost of

47、 adisposal option depend upon the actions that make up thatoption. Five actions are defined in the appendices: decontami-nation, demolition/crushing, packaging/transportation, reuse,and disposal/entombment. The appendices provide the meth-odology and supporting data to estimate the dose and cost ofe

48、ach action. To evaluate a disposal option, use the applicablesections in the appendices to calculate the dose and cost foreach action in the disposal option. Then sum the dose and costfrom all of the applicable actions to find the total dose and costfor that disposal option.5.6.2 The dose estimate i

49、s based on the isotopes present, theestimated or measured depth of penetration, and the disposaloption. The cost is based on factors associated with the disposaloption, such as decontamination, transportation, and disposal.The cost analysis information here does not include costavoidance through such things as schedule acceleration andreduced surveillance. Formulas and tables of unit-dose andunit-cost data for estimating the dose and cost are in theappendices. However, if site-specific information (such as costand decontamination factors) is available, it should be usedins