1、Designation: E1005 10Standard Test Method forApplication and Analysis of Radiometric Monitors forReactor Vessel Surveillance, E 706(IIIA)1This standard is issued under the fixed designation E1005; 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 method describes general procedures for measuringthe specific activities of radioactive
3、 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 identified in 2.1 and in Refs 11,24-27. The measurement results can be us
4、ed 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 gamma-ray spectrometry, althoughX-ray photon spectrometry and Beta partic
5、le 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 calibrationsource standards and the RMs, self absorption of radiation byth
6、e RM, other absorption effects, radioactive decay corrections,and burn out of the nuclide of interest (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 end of the irradiation, the half life, t
7、hemass 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 Procedures for calculation of reaction rat
8、es 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 reaction rates can be used to define the neu
9、tron 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 calculation of absolute reaction rates are
10、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 thecertified benchmark fluence rate (24-30).1.2
11、This method is intended to be used in conjunction withASTM Guide E844. The following existing or proposedASTMpractices, guides, and methods are also directly involved in thephysics-dosimetry evaluation of reactor vessel and supportstructure surveillance measurements:Master Matrix for Light-Water Rea
12、ctor Pressure VesselSurveillance Standards, E706 (O)3E853 Analysis and Interpretation of Light-Water ReactorSurveillance Results, E706 (IA)3E693 Practice for Characterizing Neutron Exposures in Ironand Low Alloy Steels in Terms of Displacements Per Atom(DPA), E706 (ID)3E185 Practice for Conducting S
13、urveillance Tests for Light-Water Nuclear Power Reactor Vessels, E706 (IF)3E1035 Practice for Determining Radiation Exposure forNuclear Reactor Vessel Support Structures, E706 (IG)3E636 Practice for Conducting Supplemental SurveillanceTests for Nuclear Power Reactor Vessels, E706 (IH)3E944 Guide for
14、 Application of Neutron Spectrum Adjust-ment Methods in Reactor Surveillance, E706 (IIA)3E1018 Guide for Application of ASTM Evaluated CrossSection and Data File, E706 (IIB)3E482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance, E706 (IID)3E2005 Guide for the Benchma
15、rk Testing of Reactor VesselDosimetry in Standard and Reference Neutron FieldsE2006 Guide for the Benchmark Testing of Light WaterReactor CalculationsE854 Test Method for Application and Analysis of SolidState Track Recorder (SSTR) Monitors for Reactor VesselSurveillance, E706 (IIIB)31This method is
16、 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 Jan. 1, 2010. Published February 2010. Originallyapproved in 1997. Last previous edition approved in 2003
17、 as E1005031. DOI:10.1520/E1005-10.2The 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 E706.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken
18、, PA 19428-2959, United States.E910 Test Method for Application and Analysis of HeliumAccumulation Fluence Monitors for Reactor Vessel Surveil-lance, E706 (IIIC)3E1214 Application and Analysis of Temperature Monitorsfor Reactor Vessel Surveillance, E706 (IIIE)31.3 The general procedures in this meth
19、od are applicable tothe measurement of radioactivity in RMs that satisfy thespecific constraints and conditions imposed for their analysis.More detailed procedures for 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 monito
20、rstandard methods, are intended for use by knowledgeablepersons who are intimately familiar with the procedures,equipment, and techniques necessary to achieve high precisionand accuracy in radioactivity measurements.1.5 The values stated in SI units are to be regarded asstandard. No other units of m
21、easurement are included in thisstandard.1.6 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 regulatory
22、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 (24-30)27
23、54.030 99.85527Al(n,a)24Na 0.62356 (17) d 1368.633 99.9936 1.00 TR E2662754.030 99.85532S(n,p)32P 14.262 (14) d =694.9 100. 0.9502 (9) TR E26545Sc(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 E5261120.545 99.987447Ti(n,p
24、)47Sc 3.3492 (1) d 159.381 68.3 0.0744 (2) TR E52648Ti(n,p)48Sc 43.67 (9) h 983.526 100.0 0.7372 (3) TR E5261037.522 97.51312.120 100.055Mn(n,2n)54Mn 312.11 (5) d 834.843 99.9758 1.00 TR E261, E263(24-30)54Fe(n,p)54Mn 312.11 (5) d 834.843 99.9758 0.05845 (35) TR E26354Fe(n,g)55Fe 2.73 (3) y 5.888 8.
25、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 E262, E4811332.5
26、02 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 E264863.959 0.691674.730 0.5199.15 (10) h (meta) 24.889 0.036960Ni(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
27、.01(meta) 826.28 0.00768E1005 102TABLE 1 ContinuedDosimetryReactionsResidual NucleusTarget Atom NaturalAbundanceA31DetectorResponseBASTMStandard orRef.Half-lifeC,A,DEgD(keV)YieldD(%)g/Reaction1332.501 0.242158.77 0.0007263Cu(n,g)64Cu 12.700 (2) h 1345.77 0.47336 0.6917 (3) NTR (24-30)63Cu(n,a)60Co 1
28、925.5 (5) d 1173.238 99.857 0.6917 (3) TR E5231332.502 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)109Ag(n,g)110mAg 249.76
29、 (4) d 116.48 0.00799 0.48161 (8) NTR E481884.685 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 E261, E2621097.3 56.2104818.7 11.47842112.1 15.5296115ln(n,n8)115mln 4.486 (4) h 336.241 45.9 0.9571 (5) TR (24-30)497.370
30、0.047181Ta(n,g)182Ta 114.43 (3) d 1121.3008 34.9 0.99988 (2) NTR E2621189.0503 16.2251221.4066 26.9777197Au(n,g)198Au 2.69517 (21) d 1087.6904 0.159045 1.00 NTR E261, E262675.8874 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 0.17499.02 0.21699.901 0.6876
31、4.4 0.120233Pa 26.967 (2) d 312.17 38.6FM(n,f)144Ce 284.893 (8) d 133.515 11.09 ENTR, TR E704, E70580.120 1.36407 (24-30)(see Table 2)FM(n,f)140Ba 12.752 (3) d 537.261 24.4 ENTR, TR E393, E704,(see Table 2) E705140Ba140La 1.6781 (3) d 1596.21 95.4 (24-30)815.772 23.2776487.021 45.5058(see Table 2)FM
32、(n,f)137Cs 30.07 (3) y 661.660 85.1 ENTR, TR E320, E704,(see Table 2) E705137Cs137mBa 2.552 (1) m 661.660 90.11 (24-30)(see Table 2)FM(n,f)106Ru 373.59 (15) d ENTR, TR E704, E705(see Table 2) (24-30)106Ru106Rh 29.80 (8) s 511.8605 20.4E1005 103TABLE 1 ContinuedDosimetryReactionsResidual NucleusTarge
33、t Atom NaturalAbundanceA31DetectorResponseBASTMStandard orRef.Half-lifeC,A,DEgD(keV)YieldD(%)g/Reaction(see Table 2)FM(n,f)103Ru 39.26 (2) d 497.084 91.0 ENTR, TR E704, E705(see Table 2) (24-30)FM(n,f)95Zr 64.02 (5) d 756.729 54.46 ENTR, TR E704, E705724.199 44.1725 (24-30)(see Table 2)95Zr95Nb 34.9
34、97 (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.CThe time units listed for half-life are yea
35、rs (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 and239Pu (NTR) and238U,237Np, and232Th (T
36、R) target isotope or weight fraction varies with material batch.2. Referenced Documents2.1 ASTM Standards (some already identified in 1.2), in-cluding those for individual RM monitors:2.2 ASTM Standards:4E181 Test Methods for Detector Calibration andAnalysis ofRadionuclidesE185 Practice for Design o
37、f Surveillance Programs forLight-Water Moderated Nuclear Power Reactor VesselsE261 Practice for Determining Neutron Fluence, FluenceRate, and Spectra by Radioactivation TechniquesE262 Test Method for Determining Thermal Neutron Reac-tion Rates and Thermal Neutron Fluence Rates by Radio-activation Te
38、chniquesE263 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivation of IronE264 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivation of NickelE265 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32E266 Test Method fo
39、r Measuring Fast-Neutron ReactionRates by Radioactivation of AluminumE320 Test Methods for Cesium-137 in Nuclear Fuel Solu-tions by Radiochemical Analysis5E393 Test Method for Measuring Reaction Rates by Analy-sis of Barium-140 From Fission DosimetersE481 Test Method for Measuring Neutron Fluence Ra
40、tes byRadioactivation of Cobalt and SilverE482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance, E706 (IID)E523 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivation of CopperE526 Test Method for Measuring Fast-Neutron ReactionRates by Radioactivati
41、on of TitaniumE636 Guide for Conducting Supplemental SurveillanceTests for Nuclear Power Reactor Vessels, E 706 (IH)E693 Practice for Characterizing Neutron Exposures in Ironand LowAlloy Steels in Terms of Displacements PerAtom(DPA), E 706(ID)E704 Test Method for Measuring Reaction Rates by Radio-ac
42、tivation of Uranium-238E705 Test Method for Measuring Reaction Rates by Radio-activation of Neptunium-237E844 Guide for Sensor Set Design and Irradiation forReactor Surveillance, E 706(IIC)E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)E854 Test Me
43、thod for Application and Analysis of SolidState Track Recorder (SSTR) Monitors for Reactor Sur-veillance, E706(IIIB)E910 Test Method for Application and Analysis of HeliumAccumulation Fluence Monitors for Reactor Vessel Sur-veillance, E706 (IIIC)E944 Guide for Application of Neutron Spectrum Adjust-
44、ment Methods in Reactor Surveillance, E 706 (IIA)E1018 Guide for Application of ASTM Evaluated CrossSection Data File, Matrix E706 (IIB)E1035 Practice for Determining Neutron Exposures forNuclear Reactor Vessel Support StructuresE1214 Guide for Use of Melt Wire Temperature Monitorsfor Reactor Vessel
45、 Surveillance, E 706 (IIIE)E2005 Guide for Benchmark Testing of Reactor Dosimetryin Standard and Reference Neutron FieldsE2006 Guide for Benchmark Testing of Light Water Reac-tor Calculations2.3 ANSI Standard:4For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Custom
46、er Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.5Withdrawn. The last approved version of this historical standard is referencedon www.astm.org.E1005 104N42.14 Calibration and Usage of Germanium Detect
47、ors 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 consistent
48、geometry and used to determineneutron fluence rate (flux density), fluence and spectra by6Available from American National Standards Institute, 11 W. 42nd St., 13thFloor, New York, NY 10036.TABLE 2 Recommended Fission Yield DataAFissionable Isotope Reaction ProductCumulative Fission Yield (Energy De
49、pendent) Independent Fission Yield (Energy Dependent)0.5 MeV Thermal 0.5 MeV Thermal232Th(n,f)95Zr 5.67313 6 2.8 % 3.84804 3 1036 64 % 95Nb 5.67313 6 2.8 % 7.49008 3 1076 64 % 103Ru 0.156332 6 4.0 % 6.12007 3 1086 64 % 106Ru 0.0537306 6 11 % 1.05001 3 1046 64 % 106Rh 0.0537306 6 11 % 1.33001 3 1086 64 % 137Cs 5.84355 6 4 % 8.32609 3 1036 64 % 137mBa 5.528 6 4 % 7.63008 3 1066 64 % 140Ba 7.87647 6 2.8 % 4.82795 3 1026 64 % 140La 7.87649 6 2 % 2.71003 3 1056 64 % 144Ce 7.94699 6 4 % 4.80505 3 1036 64 % 235U(n,f)95Zr 6.4
