ASTM D3649-2006(2014) Standard Practice for High-Resolution Gamma-Ray Spectrometry of Water《水的高分辩率伽马射线光谱测定法的标准实施规程》.pdf

《ASTM D3649-2006(2014) Standard Practice for High-Resolution Gamma-Ray Spectrometry of Water《水的高分辩率伽马射线光谱测定法的标准实施规程》.pdf》由会员分享，可在线阅读，更多相关《ASTM D3649-2006(2014) Standard Practice for High-Resolution Gamma-Ray Spectrometry of Water《水的高分辩率伽马射线光谱测定法的标准实施规程》.pdf（8页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: D3649 06 (Reapproved 2014) An American National StandardStandard Practice forHigh-Resolution Gamma-Ray Spectrometry of Water1This standard is issued under the fixed designation D3649; 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 () indicates an editorial change since the last revision or reapproval.1. Scope1.1 This practice covers the measurement of gamma-rayemitting radionuclides in water by means of

3、 gamma-rayspectrometry. It is applicable to nuclides emitting gamma-rayswith energies greater than 45 keV. For typical counting systemsand sample types, activity levels of about 40 Bq are easilymeasured and sensitivities as low as 0.4 Bq are found for manynuclides. Count rates in excess of 2000 coun

4、ts per secondshould be avoided because of electronic limitations. Highcount rate samples can be accommodated by dilution, byincreasing the sample to detector distance, or by using digitalsignal processors.1.2 This practice can be used for either quantitative orrelative determinations. In relative co

5、unting work, the resultsmay be expressed by comparison with an initial concentrationof a given nuclide which is taken as 100 %. For quantitativemeasurements, the results may be expressed in terms of knownnuclidic standards for the radionuclides known to be present.This practice can also be used just

6、 for the identification ofgamma-ray emitting radionuclides in a sample without quan-tifying them. General information on radioactivity and themeasurement of radiation has been published (1,2).2Informa-tion on specific application of gamma spectrometry is alsoavailable in the literature (3-5). See al

7、so the referenced ASTMStandards in 2.1 and the related material section at the end ofthis standard.1.3 This standard does not purport to address the safetyconcerns, if any, associated with its use. It is the responsibilityof the user of this standard to establish appropriate safety andhealth practic

8、es and determine the applicability of regulatorylimitation prior to use.2. Referenced Documents2.1 ASTM Standards:3D1066 Practice for Sampling SteamD1129 Terminology Relating to WaterD2777 Practice for Determination of Precision and Bias ofApplicable Test Methods of Committee D19 on WaterD3370 Pract

9、ices for Sampling Water from Closed ConduitsD3648 Practices for the Measurement of RadioactivityD4448 Guide for Sampling Ground-Water Monitoring WellsE181 Test Methods for Detector Calibration and Analysis ofRadionuclides3. Terminology3.1 DefinitionsFor definitions of terms used in thispractice, ref

10、er to Terminology D1129. For terms not defined inthis practice or in Terminology D1129, reference may be madeto other published glossaries.4. Summary of Practice4.1 Gamma ray spectra are measured with modular equip-ment consisting of a detector, high-voltage power supply,preamplifier, amplifier and

11、analog-to-digital converter (or digi-tal signal processor), multichannel analyzer, as well as acomputer with display.4.2 High-purity germanium (HPGe) detectors, p-type orn-type, are used for the analysis of complex gamma-ray spectrabecause of their excellent energy resolution. These germaniumsystems

12、, however, are characterized by high cost and requirecooling. Liquid nitrogen or electromechanical cooling, or both,can be used.4.3 In a germanium semiconductor detector, gamma-rayphotons produce electron-hole pairs. The charged pair is thencollected by an applied electric field. A very stable low n

13、oisepreamplifier is needed to amplify the pulses of electric charge1This practice is under the jurisdiction of ASTM Committee D19 on Water andis the direct responsibility of Subcommittee D19.04 on Methods of RadiochemicalAnalysis.Current edition approved June 1, 2014. Published July 2014. Originally

14、 approvedin 1978. Last previous edition approved in 2006 as D3649 06. DOI: 10.1520/D3649-06R14.2The boldface numbers in parentheses refer to a list of references at the end ofthis standard.3For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at servic

15、eastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1resulting from gamma photon interactions. The output from

16、thepreamplifier is directly proportional to the energy deposited bythe incident gamma-ray. These current pulses are fed into anamplifier of sufficient gain to produce voltage output pulses inthe amplitude range from 0 to 10 V.4.4 A multichannel pulse-height analyzer is used to deter-mine the amplitu

17、de of each pulse originating in the detector,and accumulates in a memory the number of pulses in eachamplitude band (or channel) in a given counting time. Com-puterized systems with stored programs and interface hardwarecan accomplish the same functions as hardwired multichannelanalyzers. The primar

18、y advantages of the computerized systeminclude the capability of programming the multi-channel ana-lyzer functions and the ability to immediately perform datareduction calculations using the spectral data stored in thecomputer memory or mass storage device. Fora0to2-MeVspectrum, 4000 or more channel

19、s are typically needed in orderto fully utilize a germanium detectors excellent energy reso-lution.4.5 The distribution of the amplitudes (pulse heights) of thepulses can be separated into two principal components. One ofthese components has a nearly Gaussian distribution and is theresult of total a

20、bsorption of the gamma-ray energy in thedetector. This peak is normally referred to as the full-energypeak or photopeak. The other component is a continuous onelower in energy than that of the photopeak. This continuouscurve is referred to as the Compton continuum and is due tointeractions wherein t

21、he gamma photons deposit only part oftheir energy in the detector. These two portions of the curve areshown in Fig. 1. Other peaks, such as escape peaks, backscat-tered gamma rays or X rays from shields, are often superim-posed on the Compton continuum. Escape peaks will bepresent when gamma-rays wi

22、th energies greater than 1.02 MeVare emitted from the sample. The positron formed in pairproduction is usually annihilated in the detector and one orboth of the 511keV annihilation quanta may escape from thedetector without interaction. This condition will cause single ordouble escape peaks at energ

23、ies of 0.511 or 1.022 MeV lessthan the photopeak energy. In the plot of pulse height versuscount rate, the size and location of the photopeak on the pulseheight axis is proportional to the number and energy of theincident photons, and is the basis for the quantitative andqualitative application of t

24、he spectrometer. The Comptoncontinuum serves no useful purpose in photopeak analysis andmust be subtracted when peaks are analyzed.4.6 If the analysis is being directed and monitored by anonline computer program, the analysis period may be termi-nated by prerequisites incorporated in the program. If

25、 theanalysis is being performed with a modern multichannelanalyzer, analysis may be terminated when a preselected timeor total counts in a region of interest or in a specified channelis reached. Visual inspection of a display of accumulated datacan also be used as a criterion for manually terminatin

26、g theanalysis on either type of data acquisition systems.4.7 Upon completion of the analysis, the spectral data areinterpreted and reduced to include activity of Bq (disintegra-tion per second) or related units suited to the particularapplication. At this time the spectral data may be inspected toid

27、entify the gamma-ray emitters present. This is accomplishedby reading the channel number from the x-axis and convertingto gamma-ray energy by multiplying by the appropriate keV/channel (system gain). In some systems the channel number orgamma-ray energy in keV can be displayed for any selectedchanne

28、l. Identification of nuclides may be aided by catalogs ofgamma-ray spectra and other nuclear data tabulations (3,6-8).4.7.1 Computer programs for data reduction have been usedextensively although calculations for some applications can beperformed effectively with the aid of a scientific calculator.D

29、ata reduction of spectra taken with germanium spectrometrysystems is usually accomplished by integration of the photo-peaks above a definable background (or baseline) and subse-quent activity calculations using a library which includes datasuch as nuclide name, half-life, gamma-ray energies, andabso

30、lute gamma intensity.FIG. 1 Cesium-137 SpectrumD3649 06 (2014)25. Significance and Use5.1 Gamma-ray spectrometry is of use in identifying radio-nuclides and in making quantitative measurements. Use of asemiconductor detector is necessary for high-resolution mea-surements.5.2 Variation of the physica

31、l geometry of the sample and itsrelationship with the detector will produce both qualitative andquantitative variations in the gamma-ray spectrum. To ad-equately account for these geometry effects, calibrations aredesigned to duplicate all conditions including source-to-detector distance, sample sha

32、pe and size, and sample matrixencountered when samples are measured.5.3 Since some spectrometry systems are calibrated at manydiscrete distances from the detector, a wide range of activitylevels can be measured on the same detector. For high-levelsamples, extremely low-efficiency geometries may be u

33、sed.Quantitative measurements can be made accurately and pre-cisely when high activity level samples are placed at distancesof 10 cm or more from the detector.5.4 Electronic problems, such as erroneous deadtimecorrection, loss of resolution, and random summing, may beavoided by keeping the gross cou

34、nt rate below 2000 counts persecond (s1) and also keeping the deadtime of the analyzerbelow 5 %. Total counting time is governed by the radioactiv-ity of the sample, the detector to source distance and theacceptable Poisson counting uncertainty.6. Interferences6.1 In complex mixtures of gamma-ray em

35、itters, the degreeof interference of one nuclide in the determination of anotheris governed by several factors. If the gamma-ray emission ratesfrom different radionuclides are similar, interference will occurwhen the photopeaks are not completely resolved and overlap.If the nuclides are present in t

36、he mixture in unequal portionsradiometrically, and if nuclides of higher gamma-ray energiesare predominant, there are serious interferences with theinterpretation of minor, less energetic gamma-ray photopeaks.The complexity of the analysis method is due to the resolutionof these interferences and, t

37、hus, one of the main reasons forcomputerized systems.6.2 Cascade summing may occur when nuclides that decayby a gamma-ray cascade are analyzed. Cobalt-60 is an ex-ample; 1172 and 1333-keV gamma rays from the same decaymay enter the detector to produce a sum peak at 2505 keV andcause the loss of coun

38、ts from the other two peaks. Cascadesumming may be reduced by increasing the source to detectordistance. Summing is more significant if a well-type detector isused.6.3 Random summing is a function of counting rate andoccurs in all measurements. The random summing rate isproportional to the total cou

39、nt squared and the resolving timeof the detector. For most systems random summing losses canbe held to less than 1 % by limiting the total counting rate to2000 counts per second (s1). Refer to Test Methods E181 formore information.6.4 The density of the sample is another factor that caneffect quanti

40、tative results. Errors from this source can beavoided by preparing the standards for calibration in solutionsor other matrices with a density comparable to the samplebeing analyzed.7. Apparatus7.1 Gamma Ray Spectrometer, consisting of the followingcomponents:7.1.1 Detector Assembly:7.1.1.1 Germanium

41、 DetectorThe detector may have avolume of about 50 to 150 cm3, with a full width at one-half thepeak maximum (FWHM) less than 2.2 keV at 1332 keV,certified by the manufacturer. A charge-sensitive preamplifierusing low noise field effect transistors should be an integralpart of the detector assembly.

42、 A convenient support should beprovided for samples of the desired form.7.1.1.2 ShieldThe detector assembly may be surroundedby an external radiation shield made of a dense metal,equivalent to 102 mm of lead in gamma-ray attenuationcapability. It is desirable that the inner walls of the shield be at

43、least 127 mm distant from the detector surfaces to reducebackscatter. If the shield is made of lead or a lead liner, theshield may have a graded inner shield of 1.6 mm of cadmiumor tin lined with 0.4 mm of copper, to attenuate the 88-keV PbX-rays. The shield should have a door or port for inserting

44、andremoving samples.7.1.1.3 High Voltage Power/Bias SupplyThe bias supplyrequired for germanium detectors usually provides a voltage upto 5000 V and up to 100 A. The power supply should beregulated to 0.1 % with a ripple of not more than 0.01 %. Linenoise caused by other equipment should be removed

45、with rffilters and additional regulators.7.1.1.4 AmplifierAn amplifier compatible with the pream-plifier and with the pulse-height analyzer shall be provided.7.1.2 Data Acquisition and Storage Equipment:7.1.2.1 Data AcquisitionsA multichannel pulse-heightanalyzer (MCA) or stand-alone analog-to-digit

46、al-converter(ADC) under software control of a separate computer, per-forms many functions required for gamma-ray spectrometry.An MCA or computer collects the data, provides a visualdisplay, and outputs final results or raw data for later analysis.The four major components of an MCA are the ADC, them

47、emory, control, and input/output. More recently, digitalsignal processors (DSP) can directly amplify and digitizesignals from the preamplifier, replacing individual amplifierand ADC components. The ADC digitizes the analog pulsesfrom the amplifier. These pulses represent energy. The digitalresult is

48、 used by the MCAto select a memory location (channelnumber) which is used to store the number of events whichhave occurred with that energy. Simple data analysis andcontrol of the MCA is accomplished with microprocessors.These processors control the input/output, channel summingover set regions of i

49、nterest, and system energy calibration toname a few examples.7.1.2.2 Data StorageBecause of the use of microproces-sors modern MCAs provide a wide range of input and output(I/O) capabilities.D3649 06 (2014)38. Sampling8.1 Collect the sample in accordance with Practice D1066,Practices D3370, Guide D4448, or other documented proce-dures.8.2 Preserve the sample in a radioactively homogeneousstate.Asample can be made radioactively homogeneous by theaddition of a reagent in which the radionuclides or compoundsof the radionuclides present would be soluble in large concen-tra