1、Designation: E 1005 03e1Standard Test Method forApplication and Analysis of Radiometric Monitors forReactor Vessel Surveillance, E 706(IIIA)1This standard is issued under the fixed designation E 1005; the number immediately following the designation indicates the year oforiginal adoption or, in the
2、case 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.e1NOTEThe Referenced Documents were updated editorially in July 2006.1. Scope1.1 This method descri
3、bes general procedures for measuringthe specific activities of radioactive nuclides produced inradiometric monitors (RMs) by nuclear reactions inducedduring surveillance exposures for reactor vessels and supportstructures. More detailed procedures for individual RMs areprovided in separate standards
4、 identified in 2.1 and in Refs 11,24-27. The measurement results can be used to define corre-sponding neutron induced reaction rates that can in turn beused to characterize the irradiation environment of the reactorvessel and support structure. The principal measurement tech-nique is high resolution
5、 gamma-ray spectrometry, althoughX-ray photon spectrometry and Beta particle counting are usedto a lesser degree for specific RMs (1-29).21.1.1 The measurement procedures include corrections fordetector background radiation, random and true coincidencesumming losses, differences in geometry between
6、calibrationsource standards and the RMs, self absorption of radiation bythe RM, other absorption effects, and radioactive decay cor-rections (1-10, 12-22).1.1.2 Specific activities are calculated by taking into ac-count the time duration of the count, the elapsed time betweenstart of count and the e
7、nd of the irradiation, the half life, themass of the target nuclide in the RM, and the branchingintensities of the radiation of interest. Using the appropriatehalf life and known conditions of the irradiation, the specificactivities may be converted into corresponding reaction rates(24-30).1.1.3 Pro
8、cedures for calculation of reaction rates from theradioactivity measurements and the irradiation power timehistory are included. A reaction rate can be converted toneutron fluence rate and fluence using the appropriate integralcross section and effective irradiation time values, and, withother react
9、ion rates can be used to define the neutron spectrumthrough the use of suitable computer programs (24-30).1.1.4 The use of benchmark neutron fields for calibration ofRMs can reduce significantly or eliminate systematic errorssince many parameters, and their respective uncertainties,required for calc
10、ulation of absolute reaction rates are commonto both the benchmark and test measurements and therefore areself canceling. The benchmark equivalent fluence rates, for theenvironment tested, can be calculated from a direct ratio of themeasured saturated activities in the two environments and thecertif
11、ied benchmark fluence rate (24-30).1.2 This method is intended to be used in conjunction withASTM Guide E 844. The following existing or proposedASTM practices, guides, and methods are also directly in-volved in the physics-dosimetry evaluation of reactor vesseland support structure surveillance mea
12、surements:Master Matrix for Light-Water Reactor Pressure VesselSurveillance Standards, E 706 (O)3E 853 Analysis and Interpretation of Light-Water ReactorSurveillance Results, E 706 (IA)3E 560 Practice for Extrapolating Reactor Vessel SurveillanceDosimetry Results, E 706 (IC)3E 693 Practice for Chara
13、cterizing Neutron Exposures in Ironand Low Alloy Steels in Terms of Displacements Per Atom(DPA), E 706 (ID)3E 185 Practice for Conducting Surveillance Tests for Light-Water Nuclear Power Reactor Vessels, E 706 (IF)3E 1035 Practice for Determining Radiation Exposure forNuclear Reactor Vessel Support
14、Structures, E 706 (IG)3E 636 Practice for Conducting Supplemental SurveillanceTests for Nuclear Power Reactor Vessels, E 706 (IH)3E 944 Guide for Application of Neutron Spectrum Adjust-ment Methods in Reactor Surveillance, E 706 (IIA)3E 1018 Guide for Application of ASTM Evaluated CrossSection and D
15、ata File, E 706 (IIB)31This method is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.05 on Nuclear Radiation Metrology.Current edition approved Feb. 10, 2003. Published May 2003. Originallyapproved in 1997. Last
16、previous edition approved in 1997 as E 100597.2The boldface numbers in parentheses refer to the list of references appended tothis method.3The reference in parentheses refers to Section 5 as well as Figs. 1 and 2 ofMatrix E 706.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West
17、Conshohocken, PA 19428-2959, United States.E 482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance, E 706 (IID)3E 2005 Guide for the Benchmark Testing of Reactor VesselDosimetry in Standard and Reference Neutron FieldsE 2006 Guide for the Benchmark Testing of Light Wa
18、terReactor CalculationsE 854 Test Method for Application and Analysis of SolidState Track Recorder (SSTR) Monitors for Reactor VesselSurveillance, E 706 (IIIB)3E 910 Test Method for Application and Analysis of HeliumAccumulation Fluence Monitors for Reactor Vessel Surveil-lance, E 706 (IIIC)3E1214 A
19、pplication and Analysis of Temperature Monitorsfor Reactor Vessel Surveillance, E 706 (IIIE)31.3 The general procedures in this method are applicable tothe measurement of radioactivity in RMs that satisfy thespecific constraints and conditions imposed for their analysis.More detailed procedures for
20、individual RM monitors areidentified in 2.1 and in Refs 11, 24-27 (see Table 1).1.4 This method, along with the individual RM monitorstandard methods, are intended for use by knowledgeablepersons who are intimately familiar with the procedures,equipment, and techniques necessary to achieve high prec
21、isionand accuracy in radioactivity measurements.1.5 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 standard to establish appro-priate safety and health practices and determine the applica-bility of reg
22、ulatory limitations prior to use.TABLE 1 Radiometric Monitors Proposed for Reactor Vessel SurveillanceDosimetryReactionsResidual NucleusTarget Atom NaturalAbundanceA31DetectorResponseBASTMStandard orRef.Half-lifeC,A,DEgD(keV)YieldD(%)g/Reaction23Na(n,g)24Na 0.62356 (17) d 1368.633 99.9936 1.00 NTR (
23、24-30)2754.030 99.85527Al(n,a)24Na 0.62356 (17) d 1368.633 99.9936 1.00 TR E 2662754.030 99.85532S(n,p)32P 14.262 (14) d =694.9 100. 0.9502 (9) TR E 26545Sc(n,g)46Sc 83.79 (4) d 889.277 99.9844 1.00 NTR (24-30)1120.545 99.987446Ti(n,p)46Sc 83.79 (4) d 889.277 99.9844 0.0825 (3) TR E 5261120.545 99.9
24、87447Ti(n,p)47Sc 3.3492 (1) d 159.381 68.3 0.0744 (2) TR E 52648Ti(n,p)48Sc 43.67 (9) h 983.526 100.0 0.7372 (3) TR E 5261037.522 97.51312.120 100.055Mn(n,2n)54Mn 312.11 (5) d 834.843 99.9758 1.00 TR E 261, E 263(24-30)54Fe(n,p)54Mn 312.11 (5) d 834.843 99.9758 0.05845 (35) TR E 26354Fe(n,g)55Fe 2.7
25、3 (3) y 5.888 8.2 0.05845 (35) NTR (24-30)5.899 16.26.490 2.8656Fe(n,p)56Mn 2.5789 (1) hr 846.754 98.87 0.91754 (36) TR (24-30)1810.72 27.189252113.05 14.3361558Fe(n,g)59Fe 44.472 (8) d 1099.251 56.5 0.00282 (4) NTR (24-30)1291.596 43.21481.7 0.05959Co(n,g)60Co 1925.5 (5) d 1173.238 99.857 1.00 NTR
26、E 262, E 4811332.502 99.98310.467 (6) m 58.603 2.01(meta) 826.28 0.007681332.501 0.242158.77 0.0007258Ni(n,p)58Co 70.82 (3) d 810.775 99.45 0.68077 (9) TR E 264863.959 0.691674.730 0.5199.15 (10) h (meta) 24.889 0.0369E100503e12TABLE 1 ContinuedDosimetryReactionsResidual NucleusTarget Atom NaturalAb
27、undanceA31DetectorResponseBASTMStandard orRef.Half-lifeC,A,DEgD(keV)YieldD(%)g/Reaction60Ni(n,p)60Co 1925.5 (5) d 1173.238 99.857 0.26223 (8) TR (24-30)1332.502 99.98310.467 (6) m 58.603 2.01(meta) 826.28 0.007681332.501 0.242158.77 0.0007263Cu(n,g)64Cu 12.700 (2) h 1345.77 0.47336 0.6917 (3) NTR (2
28、4-30)63Cu(n,a)60Co 1925.5 (5) d 1173.238 99.857 0.6917 (3) TR E 5231332.502 99.98310.467 (6) m 58.603 2.01(meta) 826.33 0.00581332.501 0.252158.86 0.0008893Nb(n,n8)93mNb 5.89 (5) 3 103d 30.77 0.000549 1.00 TR (11, 24-30)16.52 (Ka1,2) 9.25103Rh(n,n8)103mRh 56.114 (9) m 39.755 0.0684 1.00 TR (24-30)10
29、9Ag(n,g)110mAg 249.76 (4) d 116.48 0.00799 0.48161 (8) NTR E 481884.685 72.192937.493 34.13141384.300 24.12041505.040 12.95321475.788 3.96868115ln(n,g)116mln 54.29 (17) m 1293.54 84.4 0.9571 (5) NTR E 261, E 2621097.3 56.2104818.7 11.47842112.1 15.5296115ln(n,n8)115mln 4.486 (4) h 336.241 45.9 0.957
30、1 (5) TR (24-30)497.370 0.047181Ta(n,g)182Ta 114.43 (3) d 1121.3008 34.9 0.99988 (2) NTR E 2621189.0503 16.2251221.4066 26.9777197Au(n,g)198Au 2.69517 (21) d 1087.6904 0.159045 1.00 NTR E 261, E 262675.8874 0.8038278 (24-30)411.804 95.57232Th(n,g)233Th 22.3 (1) m 890.1 0.14 1.00 NTR (24-30)490.80 0.
31、17499.02 0.21699.901 0.68764.4 0.120233Pa 26.967 (2) d 312.17 38.6FM(n,f)144Ce 284.893 (8) d 133.515 11.09 ENTR, TR E 704, E 70580.120 1.36407 (24-30)(see Table 2)FM(n,f)140Ba 12.752 (3) d 537.261 24.4 ENTR, TR E 393, E 704,(see Table 2) E 705140Ba140La 1.6781 (3) d 1596.21 95.4 (24-30)815.772 23.27
32、76487.021 45.5058(see Table 2)FM(n,f)137Cs 30.07 (3) y 661.660 85.1 ENTR, TR E 320, E 704,(see Table 2) E 705137Cs137mBa 2.552 (1) m 661.660 90.11 (24-30)(see Table 2)FM(n,f)106Ru 373.59 (15) d ENTR, TR E 704, E 705E100503e13TABLE 1 ContinuedDosimetryReactionsResidual NucleusTarget Atom NaturalAbund
33、anceA31DetectorResponseBASTMStandard orRef.Half-lifeC,A,DEgD(keV)YieldD(%)g/Reaction(see Table 2) (24-30)106Ru106Rh 29.80 (8) s 511.8605 20.4(see Table 2)FM(n,f)103Ru 39.26 (2) d 497.084 91.0 ENTR, TR E 704, E 705(see Table 2) (24-30)FM(n,f)95Zr 64.02 (5) d 756.729 54.46 ENTR, TR E 704, E 705724.199
34、 44.1725 (24-30)(see Table 2)95Zr95Nb 34.997 (6) d 765.807 99.81(see Table 2)AThe numbers in parentheses following some given values is the uncertainty in the last digit(s) of the value: 0.729 (8) means 0.7296 0.008, 70.8 (1) means 70.8 6 0.1.BNTR = Non-Threshold Response, TR = Threshold Response.CT
35、he time units listed for half-life are years (y), days (d), hours (h), minutes (m), and seconds (s).DThe nuclear data has been drawn from several primary sources including References (31), (33) and (34). Reference (32) summarizes the source of the selected nuclearconstants.EFM = Fission Monitor:235U
36、 and239Pu (NTR) and238U,237Np, and232Th (TR) target isotope or weight fraction varies with material batch.2. Referenced Documents2.1 ASTM Standards not identified in 1.2, including thosefor individual RM monitors:2.2 ASTM Standards:4E 181 Test Methods for Detector Calibration and Analysisof Radionuc
37、lidesE 261 Practice for Determining Neutron Fluence, FluenceRate, and Spectra by Radioactivation TechniquesE 262 Test Method for Determining Thermal Neutron Re-action and Fluence Rates by Radioactivation TechniquesE 263 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivation of IronE
38、 264 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivation of NickelE 265 Test Method for Measuring Reaction Rates andFast-Neutron Fluences by Radioactivation of Sulfur-32E 266 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivation of AluminumE 320 Test Methods for
39、 Cesium-137 in Nuclear Fuel Solu-tions by Radiochemical Analysis5E 393 Test Method for Measuring Reaction Rates byAnaly-sis of Barium-140 From Fission DosimetersE 481 Test Method for Measuring Neutron Fluence Ratesby Radioactivation of Cobalt and SilverE 482 Guide for Application of Neutron Transpor
40、t Methodsfor Reactor Vessel Surveillance, E706 (IID)E 523 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivation of CopperE 526 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivation of TitaniumE 704 Test Method for Measuring Reaction Rates by Ra-dioactivation of Ur
41、anium-238E 705 Test Method for Measuring Reaction Rates by Ra-dioactivation of Neptunium-237E 844 Guide for Sensor Set Design and Irradiation forReactor Surveillance, E 706(IIC)E 944 Guide for Application of Neutron Spectrum Adjust-ment Methods in Reactor Surveillance, E 706 (IIA)E 1018 Guide for Ap
42、plication of ASTM Evaluated CrossSection Data File, Matrix E 706 (IIB)E 2005 Guide for Benchmark Testing of Reactor Dosimetryin Standard and Reference Neutron FieldsE 2006 Guide for Benchmark Testing of Light Water Reac-tor Calculations2.3 ANSI Standard:N42.14 Calibration and Usage of Germanium Dete
43、ctors forMeasurement of Gamma-Ray Emission Rates of Radio-nuclides63. Terminology3.1 Definitions:3.1.1 radiometric monitor (RM), dosimeter, foila smallquantity of material consisting of or containing an accuratelyknown mass of a specific target nuclide. Usually fabricated ina specified and consisten
44、t geometry and used to determineneutron fluence rate (flux density), fluence and spectra bymeasuring a specific radioactive neutron-induced reactionproduct.Asingle RM may contain more than one target nuclideor have more than one specific reaction product.3.1.2 calibration standarda calibrated radioa
45、ctive sourcestandardized using an absolute calibration method or byrigorous comparison to a national or certified radioactivitystandard source.4For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards vo
46、lume information, refer to the standards Document Summary page onthe ASTM website.5Withdrawn.6Available from American National Standards Institute, 11 W. 42nd St., 13thFloor, New York, NY 10036.E100503e143.1.3 national radioactivity standard sourcea calibratedradioactive source prepared and distribu
47、ted as a standardreference material by the National Institute of Standards andTechnology (NIST).3.1.4 certified radioactivity standard sourcea calibratedradioactive source, with stated accuracy, whose calibration istraceable to a national radioactivity measurements system.3.1.5 check source, control
48、 standarda radioactivitysource, not necessarily calibrated, which is used as a workingreference to verify the continuing satisfactory operation of aninstrument.3.1.6 FWHM (full width at half maximum)a measure ofdetector/system gamma-ray energy resolution expressed as thewidth of the gamma-ray peak d
49、istribution, in units of energy,measured at one-half the maximum peak height above thebackground.3.1.7 FWTM (full width at tenth maximum)identical toFWHM except the width is measured at one tenth the maxi-mum peak height above the background.3.1.8 resolution, gamma-rayusually expressed as theFWHM and often including a specification for the FWTM.TABLE 2 Recommended Fission Yield DataAFissile Isotope Reaction ProductCumulative Fission Yield (Energy Dependent) Independent Fission Yield (Energy Dependent)0.5 MeV Thermal 0.5 MeV Thermal232Th(n,f)95Zr 5.67313
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