ASTM E2216-2002(2008) 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 02 (Reapproved 2008)Standard 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

2、of revision, 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.INTRODUCTIONNumerous nuclear facilities containing large amounts of concrete are scheduled for decontami

3、nationand decommissioning 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

4、to measurethan surface 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

5、such that a case canbe 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 es

6、timated basedon the 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

7、difficultfor activated 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 ar

8、e documentedand used 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

9、 of concrete rubble. 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

10、-commissioning. It 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 t

11、heappendices. The 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 t

12、o requestrelease 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,” (1)2from which the analys

13、ismethodology and supporting data are taken.1.3 Guide E 1760 provides a general process for release ofmaterials containing residual amounts of radioactivity. In1This guide is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of Subcom

14、mitteeE10.03 on Radiological Protection for Decontamination and Decommissioning ofNuclear Facilities and Components.Current edition approved Jan. 1, 2008. Published March 2008. Originallyapproved in 2002. Last previous edition approved in 20028 as E 221602.2The boldface numbers in parentheses refer

15、to a list of references at the end ofthis standard.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.addition, Guide E 1278 provides a general process for analyz-ing radioactive pathways. This standard guide is intended foruse in conju

16、nction with Guides E 1760 and E 1278, andprovides a more detailed approach for the release of concrete.2. Referenced Documents2.1 ASTM Standards:3E 1278 Guide for Radioactive Pathway Methodology forRelease of Sites Following Decommissioning4E 1760 Guide for Unrestricted Disposition of Bulk Materi-al

17、s Containing Residual Amounts of RadioactivityE 1893 Guide for Selection and Use of Portable Radiologi-cal Survey Instruments for Performing In Situ RadiologicalAssessments in Support of Decommissioning2.2 ANSI Standards:5ANSI/HPS N13.12 Surface and Volume Radioactivity Stan-dards for ClearanceANSI/

18、HPS N13.2 Guide for Administrative Practices inRadiation Monitoring2.3 IAEA Standards:6Safety Series No. 111-P-1.1 Application of Exemption Prin-ciples to the Recycle and Reuse of Materials from NuclearFacilitiesIAEA-TECDOC-855 Clearance Levels for Radionuclidesin Solid Materials2.4 ISO Standards:7I

19、SO-4037 X and Gamma Reference Radiations for Calibrat-ing Dosimeters and Dose-rate Meters and for Determiningtheir Response as a Function of Photon EnergyISO-6980-1 Nuclear Energy Reference beta-particle ra-diation Part 1: Methods of productionISO-6980-2 Nuclear Energy Reference beta-particle ra-dia

20、tion Part 2: Calibration fundamentals related to basicquantities characterizing the radiation fieldISO-8769 Reference Sources for the Calibration of SurfaceContamination MonitorsBeta Emitters (Maximum BetaEnergy Greater than 0.15 MeV) and Alpha EmittersISO-7503-1 Evaluation of Surface ContaminationP

21、art 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 Transition and Electron Capture Emitters, LowEnergy Beta Emitters (EBmax0.1

22、5 MeV)2.5 DOE Standards:8DOE G 441.11B Radiation Protection Programs Guide,Order 5400.5 Radiation Protection of the Public and theEnvironment, as amendedOrder 5400.5 Radiation Protection of the Public and theEnvironment, as amended2.6 U.S. Government Documents:9NUREG-1640 Radiological Assessments fo

23、r Clearance ofEquipment and Materials From Nuclear FacilitiesNUREG/CR-5512 Residual Radioactive ContaminationFrom Decommissioning10 CFR 20 Standards for Protection Against Radiation2.7 NRC Standards:10Regulatory Guide 1.86 Termination of Operating Licensesfor Nuclear Reactors3. Terminology3.1 Defini

24、tions 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 fields; the concrete itself isradioactive.3.1.2 as low as reasonably achievable (ALARA)is a pro-cess used for

25、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 the levels are as low as is reasonabletaking into account social, technical, economic, practical, andpublic p

26、olicy 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 remain under radiologicalcontrol by a regulatory agency. The release does not apply toreal property (such as re

27、al 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 contamination canbe adequately quantified in terms of activity per unit area.ANSI/HPS N13.123.1.5 volumetric c

28、ontaminationradioactive contaminationresiding in or throughout the volume of an item. Volumetriccontamination can result from neutron activation or from thepenetration of radioactive contamination into cracks or interiorsurfaces within the interior matrix of an item. ANSI/HPSN13.124. Significance an

29、d 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 rubbelized where it is difficult to measure the radiationlevels and not easy to remove surface contamination to

30、 reduceradiation levels after concrete has been rubbelized.3For 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.4W

31、ithdrawn.5Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.6Available from InternationalAtomic EnergyAgency, Wagramerstrasse, PO Box100 A-1400, Vienna, Austria.7Available from International Organization for Standardization

32、(ISO), 1 rue deVaremb, Case postale 56, CH-1211, Geneva 20, Switzerland.8Available from United States Department of Energy, National TechnicalInformation Service, US Dept. of Commerce, Springfield, VA 22161.9Available from the Superintendent of Documents, US Government PrintingOffice, Washington, DC

33、 20402.10Available from Nuclear Regulatory Commission, Public Document Room,1717H St. NW, Washington, DC 20555.E 2216 02 (2008)24.3 This standard guide applies to surface or volumetricallycontaminated concrete, where the depth of contamination canbe measured or estimated based on the history of the

34、concrete.4.4 This standard guide does not apply to the reinforcementbar (rebar) found in concrete. Although most concrete containsrebar, 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 Gen

35、eral unit-dose and unit-cost data to support thecalculations is provided in the appendices of this standardguide. However, if site-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

36、 disposal of concrete and to future residents ofdisposal areas. It does not include dose to radiation workersalready involved in 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 co

37、st and dose to radiation workers could be added in tofind an overall cost and dose for each option.5. Elements of the Release Process5.1 This standard guide describes the steps of an overallrelease process for radioactively contaminated concrete fromdecommissioning nuclear facilities. As one of the

38、steps, itprovides a method and supporting data to estimate the dose andcost impacts for various disposal options. This data can 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 contami

39、nated materialmust meet all criteria of the governing regulatory agencies.5.2 Ref (2) described a 10-step release process in thepublication, “Authorized Release of DOEs Non-Real Prop-erty: Process and Approach.” These 10 steps are the basis forthe, “Protocol for Development of Authorized Release Lim

40、itsfor Concrete at U.S. Department of Energy Sites” (1) and alsofor this guide.5.2.1 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 authori

41、zed or supplemental guidelines;5.2.5 Compile and submit application for approval 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 supplementalguideline

42、s have been met; and5.2.10 Release property.5.3 Characterize Property and Prepare 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, o

43、r this can be measured. Radiologi-cal surveys must be done to determine the isotopes 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 concre

44、te is below those levels, the concrete canbe released through approved regulatory 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 an

45、d cost for various disposal optionsand select the best one. All required regulatory 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 optio

46、n, and then apply for approval torelease the material based on these data. Such 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

47、of guidelines need to be developed:5.5.1.1 Surface or volumetric contamination;5.5.1.2 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 consis

48、ts of a set of actions suchas decontamination and disposal. The dose and cost of 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 appendice

49、s provide the meth-odology and supporting data to estimate the dose and cost ofeach 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 is 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 decontamina