ASTM C1221-2010(2018) Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry《用伽马能谱法在均匀溶液中无损分析特殊核材料的标准试验方法》.pdf

《ASTM C1221-2010(2018) Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry《用伽马能谱法在均匀溶液中无损分析特殊核材料的标准试验方法》.pdf》由会员分享，可在线阅读，更多相关《ASTM C1221-2010(2018) Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry《用伽马能谱法在均匀溶液中无损分析特殊核材料的标准试验方法》.pdf（8页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: C1221 10 (Reapproved 2018)Standard Test Method forNondestructive Analysis of Special Nuclear Materials inHomogeneous Solutions by Gamma-Ray Spectrometry1This standard is issued under the fixed designation C1221; the number immediately following the designation indicates the year oforigi

2、nal adoption or, in the case of revision, the year of last revision. 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 This test method covers the determination of the con-centration

3、of gamma-ray emitting special nuclear materialsdissolved in homogeneous solutions. The test method correctsfor gamma-ray attenuation by the solution and its container bymeasurement of the transmission of a beam of gamma raysfrom an external source (Refs. (1), (2), and (3).21.2 Two solution geometrie

4、s, slab and cylinder, are consid-ered. The solution container that determines the geometry maybe either a removable or a fixed geometry container. This testmethod is limited to solution containers having walls or a topand bottom of equal transmission through which the gammarays from the external tra

5、nsmission correction source mustpass.1.3 This test method is typically applied to radionuclideconcentrations ranging from a few milligrams per litre toseveral hundred grams per litre. The assay range will be afunction of the specific activity of the nuclide of interest, thephysical characteristics o

6、f the solution container, countingequipment considerations, assay gamma-ray energies, solutionmatrix, gamma-ray branching ratios, and interferences.1.4 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this st

7、andard to establish appro-priate safety, health, and environmental practices and deter-mine the applicability of regulatory limitations prior to use.For specific hazards, see Section 9.1.5 This international standard was developed in accor-dance with internationally recognized principles on standard

8、-ization established in the Decision on Principles for theDevelopment of International Standards, Guides and Recom-mendations issued by the World Trade Organization TechnicalBarriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:3C1133/C1133M Test Method for Nondestructive Assay

9、 ofSpecial Nuclear Material in Low-Density Scrap and Wasteby Segmented Passive Gamma-Ray ScanningC1168 Practice for Preparation and Dissolution of PlutoniumMaterials for AnalysisC1490 Guide for the Selection, Training and Qualification ofNondestructive Assay (NDA) PersonnelC1592/C1592M Guide for Mak

10、ing Quality NondestructiveAssay Measurements (Withdrawn 2018)4C1673 Terminology of C26.10 Nondestructive Assay Meth-odsE181 Test Methods for Detector Calibration and Analysis ofRadionuclides2.2 ANSI Standards:5ANSI N15.20 Guide to Calibrating Nondestructive AssaySystemsANSI N15.35 Guide to Preparing

11、 Calibration Material forNondestructiveAssay Systems that Count Passive GammaRaysANSI N15.37 Guide to the Automation of NondestructiveAssay Systems for Nuclear Material ControlANSI N42.14 American National Standard for Calibrationand Use of Germanium Spectrometers for the Measure-ment of Gamma-Ray E

12、mission Rates of RadionuclidesANSI/IEEE 645 Test Procedures for High-Purity Germa-nium Detectors for Ionizing Radiation3. Terminology3.1 For definitions of terms used in this test method, refer toCommittee C26.10s Terminology standard, C1673.1This test method is under the jurisdiction ofASTM Committ

13、ee C26 on NuclearFuel Cycle and is the direct responsibility of Subcommittee C26.10 on NonDestructive Assay.Current edition approved April 1, 2018. Published April 2018. Originallyapproved in 1992. Last previous edition approved in 2010 as C1221 10. DOI:10.1520/C1221-10R18.2The boldface numbers in p

14、arentheses refer to the list of references at the end ofthis test method.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 A

15、STM website.4The last approved version of this historical standard is referenced onwww.astm.org.5Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Consho

16、hocken, PA 19428-2959. United StatesThis international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for theDevelopment of International Standards, Guides and Recommendations issued by the World Trade Orga

17、nization Technical Barriers to Trade (TBT) Committee.14. Summary of Test Method4.1 Many nuclear materials spontaneously emit gamma rayswith energies and intensities characteristic of the decayingnuclide. The analysis for these nuclear materials is accom-plished by selecting appropriate gamma rays an

18、d measuringtheir intensity to identify and quantify the nuclide.4.1.1 The gamma-ray spectrum of a portion of solution isobtained with a collimated, high resolution gamma-ray detec-tor.4.1.2 Count-rate-dependent losses are determined and cor-rections are made for these losses.4.1.3 A correction facto

19、r for gamma-ray attenuation in thesolution and its container is determined from the measurementof the transmitted intensity of an external gamma-ray source.The gamma rays from the external source have energies closeto those of the assay gamma rays emitted from the solution.Figs. 1 and 2 illustrate t

20、ypical transmission source, solution,and detector configurations. Gamma rays useful for assays of235U and239Pu are listed in Table 1.4.1.4 The relationship between the measured gamma-rayintensity and the nuclide concentration (the calibration con-stant) is determined by use of appropriate standards

21、(ANSIN15.20, ANSI N15.35, and Guide C1592/C1592M).4.2 In the event that the total element concentration isdesired and only one isotope of an element is determined (forexample,239Pu), the isotopic ratios must be measured orestimated.5. Significance and Use5.1 This test method is a nondestructive mean

22、s of determin-ing the nuclide concentration of a solution for special nuclearmaterial accountancy, nuclear safety, and process control.5.2 It is assumed that the nuclide to be analyzed is in ahomogeneous solution (Practice C1168).5.3 The transmission correction makes the test methodindependent of ma

23、trix (solution elemental composition anddensity) and useful over several orders of magnitude of nuclideconcentrations. However, a typical configuration will normallyspan only two to three orders of magnitude because of detectordynamic range.5.4 The test method assumes that the solution-detectorgeome

24、try is the same for all measured items. This can beaccomplished by requiring that the liquid height in the side-looking geometry exceeds the detector field of view defined bythe collimator. For the upward-looking geometry, a fixedsolution fill height must be maintained and vials of identicalradii mu

25、st be used unless the vial radius exceeds the field ofview defined by the collimator.5.5 Since gamma-ray systems can be automated, the testmethod can be rapid, reliable, and not labor intensive.5.6 This test method may be applicable to in-line or off-linesituations.6. Interferences6.1 Radionuclides

26、may be present in the solution, whichproduce gamma rays with energies that are the same or verynearly the same as the gamma rays suggested for nuclidemeasurement, count rate correction, or transmission correction.Thus, the corresponding peaks in the gamma-ray spectrum maybe unresolved and their area

27、s may not be easily determinedunless multiplet fitting techniques are used. In some cases, thenuclide of interest may emit other gamma rays that can be usedfor analysis or alternative transmission or count rate correctionsources may be used.6.1.1 Occasionally, a significant amount of237Np is found i

28、na plutonium solution. The237Np daughter,233Pa, emits agamma ray at 415.8 keV as well as other gamma rays in the300 to 400 keV region. These233Pa gamma rays may interferewith the analysis of239Pu at 413.7 keV and at several othernormally useful239Pu gamma-ray energies. In this case,NOTE 1The sample

29、geometry may be either cylindrical or a slab. (Notto scale.)FIG. 1 Schematic of a Sidelooking ConfigurationNOTE 1The sample geometry in this case is a slab. (Not to scale.)FIG. 2 Schematic of an Uplooking ConfigurationTABLE 1 Suggested Nuclide/Source CombinationsNuclidePeakEnergy(keV)TransmissionSou

30、rcePeakEnergy(keV)CountRateCorrectionSourcePeakEnergy(keV)235U 185.7169Yb 177.2198.0241Am 59.5239Pu 413.775Se 400.1133Ba 356.3239Pu 129.357Co 122.1136.5109Cd 88.0C1221 10 (2018)2the239Pu gamma ray at 129.3 keV may be a reasonablealternative. In addition, the 398.7 keV gamma ray from233Pamay interfer

31、e with the transmission corrections based on the400.7 keV75Se gamma-ray measurements. Multiple fittingtechniques can resolve these problems.6.1.2169Yb, used as the transmission source for235U assays,emits a 63.1 keV gamma ray that may interfere with themeasurement of the area of the peak produced by

32、 the 59.5 keVgamma ray of241Am, which is commonly used as the countrate correction source. The 63.1 keV169Yb gamma ray shouldbe attenuated by placing a cadmium absorber over the trans-mission source.109Cd may be a suitable alternative count ratecorrection source.6.1.3 In the special case of239Pu ass

33、ays using75Se as atransmission source, random coincident summing of the 136.0and 279.5 keV gamma-ray emissions from75Se produces a lowintensity sum peak at 415.5 keV that interferes with the peakarea calculation for the peak produced by the 413.7 keVgamma ray from239Pu. The effects of this sum peak

34、interfer-ence can be reduced by using absorbers to attenuate theradiation from the75Se to the lowest intensity required fortransmission measurements of acceptable precision. The prob-lem can be avoided entirely by making two separate measure-ments on each item/solution; first, measure the peak area

35、of thetransmission source with the solution in place and second,measure the peak area of the assay gamma ray while thedetector is shielded from the transmission source. An addi-tional benefit of the “dual scan” is a better signal to noise ratioin the individual spectra.6.1.4 In239Pu solutions with h

36、igh activities of241Amor237U, or both, the Compton continuum from intense 208.0keV gamma rays may make the 129.3 keV gamma ray from239Pu unusable for assays. Also, the 416.0 keV sum peak thatresults from pileup of the 208.0 keV gamma rays may interferewith the 413.7 keV gamma ray from239Pu. Use an a

37、bsorber(for example, 0.5 to 0.8 mm of tungsten) between the detectorand solution to attenuate the 208.0 keV gamma rays. This willattenuate the intensity of the lower energy gamma rays and alsoreduce the sum peak interference. The resulting239Pu assaywill be based on the 413.7 keV gamma ray.6.1.5 X-r

38、ays of approximately 88 keV from lead in theshielding may interfere with the measurement of the 88.0 keVgamma-ray peak when109Cd is used as the count rate correc-tion source. Graded shielding (4) is required to remove theinterference.6.2 Peaks may appear in the spectrum at gamma-ray ener-gies used f

39、or analysis when there is no solution present. Thismay be caused by excessive amounts of radioactive materialstored in the vicinity of the detector or by contamination of theinstrument. This can cause variable and unacceptably highbackgrounds leading to poor measurement quality.6.2.1 Remove unnecess

40、ary radioactive material from thevicinity and also restrain movement of radioactive materialaround the assay area during measurements. Shielding shouldbe provided that completely surrounds the detector with theexception of the collimator opening. Shielding opposite thedetector on the far side of the

41、 solution will also reduce theamount of ambient radiation incident on the detector.6.2.2 Use solution containers that are free of outer surfacecontamination. Remove any contamination from the instru-ment that may interfere with analyses. It may not be possible tocompletely decontaminate in-line inst

42、rumentation. In this case,the contamination should be minimized to the extent practical.6.2.3 The measurement of background should be made atvarious times during the day. Varying backgrounds can becaused by process activities that often occur on regularschedules. These time-dependent backgrounds mig

43、ht not bedetected if the background is checked at the same time eachday.6.3 High-energy gamma rays from fission products in thesolution will increase the Compton background and decreasethe precision of gamma-ray intensity measurements in thelower energy (500 keV) region of the spectrum.6.4 Low energ

44、y X- and gamma rays from either the trans-mission or count rate correction source may contribute signifi-cantly to the total system electronic pulse rate causing in-creased count rate losses and sum peak interferences. Anabsorber should be fixed between the source and detector toreduce the number of

45、 low energy X-rays detected.7. Apparatus7.1 Gamma-Ray Detector SystemGeneral guidelines forselection of detectors and signal-processing electronics arediscussed in Guide C1592/C1592M, and ANSI N42.14. Referto the References section for a list of other recommendedreferences. This system typically con

46、sists of a gamma-raydetector, spectroscopy grade amplifier, high-voltage biassupply, multi-channel analyzer, and detector collimator. Thesystem may also include an oscilloscope, a spectrum stabilizer,a computer, and a printer. General guidelines for selection ofdetectors and signal-processing electr

47、onics are discussed inGuide C1592/C1592M. Data acquisition systems are consid-ered in ANSI N15.37. It is recommended that the system beimplemented by an NDA Professional (C1490). The systemshould have the following components:7.2 High Resolution, Germanium, Gamma-RayDetectorA coaxial-type detector w

48、ith full width at halfmaximum (FWHM) resolution typically 1000 eV or better at122 keV may be used for the analysis. A planar-type detectorwith similar resolution may also be used.The stated resolutionsare for guidance only. The selection of detector type, coaxial orplanar, should be based on the usu

49、al considerations of effi-ciency and resolution required for the specific application. Testprocedures for detectors are given in Test Methods E181 andANSI/IEEE 645.7.3 Detector CollimatorThe collimator defines the field ofview of the detector to a reproducible solution geometry andshields the detector from ambient radiation. This test methodaddresses two potential solution/collimator geometries thatwill dictate the analytical expression used. Other designsrequire case-by-case assessment.7.3.1 The collimator in the slab geometry (both upwardlooking and sidelooking) is a cylin