1、Designation: E1005 15E1005 16Standard Test Method forApplication and Analysis of Radiometric Monitors forReactor Vessel Surveillance1This standard is issued under the fixed designation E1005; the number immediately following the designation indicates the year oforiginal adoption or, in the case of r
2、evision, 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 describes procedures for measuring the specific activities of radioactive nuclid
3、es produced in radiometricmonitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures. Moredetailed procedures for individual RMs are provided in separate standards identified in 2.1 and in Refs (1-5).2 The measurementresults can be used to de
4、fine corresponding neutron induced reaction rates that can in turn be used to characterize the irradiationenvironment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-rayspectrometry, although X-ray photon spectrometry and Beta particle counti
5、ng are used to a lesser degree for specific RMs (1-29).1.1.1 The measurement procedures include corrections for detector background radiation, random and true coincidencesumming losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM,o
6、ther absorption effects, radioactive decay corrections, and burn out of the nuclide of interest (6-26).1.1.2 Specific activities are calculated by taking into account the time duration of the count, the elapsed time between start ofcount and the end of the irradiation, the half life, the mass of the
7、 target nuclide in the RM, and the branching intensities of theradiation of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be convertedinto corresponding reaction rates (2-5, 28-30).1.1.3 Procedures for calculation of reaction rates fro
8、m the radioactivity measurements and the irradiation power time historyare included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section andeffective irradiation time values, and, with other reaction rates can be used to define the neutro
9、n spectrum through the use ofsuitable computer programs (2-5, 28-30).1.1.4 The use of benchmark neutron fields for calibration of RMs can reduce significantly or eliminate systematic errors sincemany parameters, and their respective uncertainties, required for calculation of absolute reaction rates
10、are common to both thebenchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environmenttested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certifiedbenchmark fluence rate (2-5,
11、28-30).1.2 This method is intended to be used in conjunction with ASTM Guide E844. The following existing or proposed ASTMpractices, guides, and methods are also directly involved in the physics-dosimetry evaluation of reactor vessel and support structuresurveillance measurements:E706 Master Matrix
12、for Light-Water Reactor Pressure Vessel Surveillance Standards, E706 (O) 3E853 Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA)3E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA),E706 (ID)3E185 Pr
13、actice for Conducting Surveillance Tests for Light-Water Nuclear Power Reactor Vessels, E706 (IF)3E1035 Practice for Determining Radiation Exposure for Nuclear Reactor Vessel Support Structures, E706 (IG)3E636 Practice for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels,
14、 E706 (IH)3E2956 Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels3E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E706 (IIA)3E1018 Guide for Application of ASTM Evaluated Cross Section and Data File, E706 (IIB)3E482 Guide for Applic
15、ation of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)31 This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05on Nuclear Radiation Metrology.Current edition approved July
16、 1, 2015Oct. 1, 2016. Published October 2015November 2016. Originally approved in 1997. Last previous edition approved in 20102015as E1005E1005 15.10. DOI: 10.1520/E1005-15.10.1520/E1005-16.2 The boldface numbers in parentheses refer to the list of references appended to this method.3 The reference
17、in parentheses refers to Section 5 as well as Figs. 1 and 2 of Matrix E706.This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Becauseit may not be technically possible to adequately
18、depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current versionof the standard as published by ASTM is to be considered the official document.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA
19、 19428-2959. United States1E2005 Guide for the Benchmark Testing of Reactor Vessel Dosimetry in Standard and Reference Neutron FieldsE2006 Guide for the Benchmark Testing of Light Water Reactor CalculationsE854 Test Method forApplication andAnalysis of Solid State Track Recorder (SSTR) Monitors for
20、Reactor Vessel Surveillance,E706 (IIIB)3E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,E706 (IIIC)3E1214 Application and Analysis of Temperature Monitors for Reactor Vessel Surveillance, E706 (IIIE) 31.3 The procedures in this te
21、st method are applicable to the measurement of radioactivity in RMs that satisfy the specificconstraints and conditions imposed for their analysis. More detailed procedures for individual RM monitors are identified in 2.1and in Refs 1-5 (see Table 1).1.4 This test method, along with the individual R
22、M monitor standard methods, are intended for use by knowledgeable personswho are intimately familiar with the procedures, equipment, and techniques necessary to achieve high precision and accuracy inradioactivity measurements.1.5 The values stated in SI units are to be regarded as standard. No other
23、 units of measurement are included in this standard,except for the energy units based on the electron volt, keV and Mev, and the time units: minute (min), hour (h), day (d), and year(a).1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is t
24、he responsibilityof the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatorylimitations prior to use.2. Referenced Documents2.1 ASTM Standards (some already identified in 1.2), including those for individual RM monitors:2.2 ASTM Sta
25、ndards:4E181 Test Methods for Detector Calibration and Analysis of RadionuclidesE185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor VesselsE261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation TechniquesE262 Test Met
26、hod for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by RadioactivationTechniquesE263 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of IronE264 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of NickelE265 Test Metho
27、d for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32E266 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of AluminumE393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission DosimetersE481 Test Method for Measuri
28、ng Neutron Fluence Rates by Radioactivation of Cobalt and SilverE482 Guide for Application of Neutron Transport Methods for Reactor Vessel SurveillanceE523 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of CopperE526 Test Method for Measuring Fast-Neutron Reaction Rates by
29、Radioactivation of TitaniumE636 Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA),E 706(ID)E704 Test Method for Measuring Reaction
30、Rates by Radioactivation of Uranium-238E705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance ResultsE854
31、Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance,E706(IIIB)E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel MaterialsE910 Test Method for Application and Analysis of Helium Accumulation Fluence M
32、onitors for Reactor Vessel Surveillance,E706 (IIIC)E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)E1035 Practice for Determining Neutron Exposures for Nuclea
33、r Reactor Vessel Support StructuresE1214 Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)E2005 Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields4 For referencedASTM standards, visit theASTM website, www.astm.org, or
34、 contactASTM Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.E1005 162TABLE 1 Radiometric Monitors Proposed for Reactor Vessel SurveillanceDosimetryReactionsResidual NucleusTarget Atom NaturalA
35、bundanceA 31DetectorResponseBASTMStandard orRefHalf-lifeC,A,D ED(keV)YieldD(%)/Reaction23Na(n,)24Na 14.9574 (20) h 1368.626 99.9935 1.00 NTR (2-5, 28-31)2754.007 99.87227Al(n,)24Na 14.9574 (20) h 1368.626 99.9935 1.00 TR (31)E2662754.007 99.87232S(n,p)32P 14.284 (14) d =694.9 100. 0.9502 (9) TR E265
36、45Sc(n,)46Sc 83.788 (22) d 889.277 99.9844 1.00 NTR (2-5, 28-31)1120.545 99.987446Ti(n,p)46Sc 83.788 (22) d 889.277 99.9844 0.0825 (3) NTR (31)E5261120.545 99.987447Ti(n,p)47Sc 3.3492 (6) 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
37、 100.055Mn(n,2n)54Mn 312.13 (3) d 834.838 99.9758 1.00 TR E261, E263(2-5, 28-30)54Fe(n,p)54Mn 312.13 (3) d 834.838 99.9758 0.05845 (35) TR E26354Fe(n,)55Fe 2.744 (9) a 5.888 8.2 0.05845 (35) NTR (2-5, 28-30)5.899 16.26.490 2.8656Fe(n,p)56Mn 2.57878 (46) h 846.764 98.85 0.91754 (36) TR (2-5, 28-30)18
38、10.73 26.88722113.09 14.234458Fe(n,)59Fe 44.495 (9) d 1099.245 56.5 0.00282 (4) NTR (2-5, 28-30)1291.590 43.21481.7 0.05959Co(n,)60Co 1925.28 (14) d 1173.228 99.85 1.00 NTR E262, E4811332.492 99.982610.467 (6) min 58.603 2.07(meta) 826.10 0.007751332.492 0.252158.57 0.0007558Ni(n,p)58Co 70.86 (6) d
39、810.7593 99.45 0.68077 (9) TR E264863.951 0.691674.725 0.5079.10 (9) h (meta) 24.889 0.039760Ni(n,p)60Co 1925.28 (14) d 1173.238 99.85 0.26223 (8) TR (2-5, 28-30)1332.492 99.982610.467 (6) m 58.603 2.07(meta) 826.10 0.007751332.492 0.252158.57 0.0007563Cu(n,)64Cu 12.701 (2) h 1345.77 0.475395 0.6917
40、 (3) NTR (2-5, 28-30)63Cu(n,)60Co 1925.28 (14) d 1173.238 99.85 0.6917 (3) TR E5231332.492 99.982610.467 (6) min 58.603 2.07(meta) 826.10 0.007751332.492 0.252158.57 0.0007593Nb(n,n)93mNb 5.89 (5) 103 d 30.77 0.000591 1.00 TR (1-5, 28-30)16.52 (K1,2) 9.25103Rh(n,n)103mRh 56.114 (20) min 39.755 0.068
41、4 1.00 TR (2-5, 28-30)109Ag(n,)110mAg 249.78 (2) d 116.48 0.00799 0.48161 (8) NTR E481884.6781 74.0E1005 163E2006 Guide for Benchmark Testing of Light Water Reactor CalculationsTABLE 1 ContinuedDosimetryReactionsResidual NucleusTarget Atom NaturalAbundanceA 31DetectorResponseBASTMStandard orRefHalf-
42、lifeC,A,D ED(keV)YieldD(%)/Reaction937.485 34.511384.2931 24.471505.028 13.161475.7792 4.03115ln(n,)116mln 54.29 (17) min 1293.56 84.8 0.9571 (5) NTR E261, E2621097.28 58.512818.68 12.1262112.19 15.094115ln(n,n)115mln 4.486 (4) h 336.241 45.9 0.9571 (5) TR (2-5, 28-30)497.370 0.047181Ta(n,)182Ta 114
43、.74 (12) d 1121.290 35.24 0.9998799 (32) NTR E2621189.040 16.4851221.395 27.230197Au(n,)198Au 2.69517 (21) d 1087.6842 0.159 1.00 NTR E261, E262675.8836 0.806 (2-5, 28-30)411.802504 95.54232Th(n,)233Th 21.83 (4) min 890.1 0.14 1.00 NTR (2-5, 28-30)490.80 0.17499.02 0.21699.901 0.68764.4 0.120. . . .
44、233Pa 26.975 (13) d 311.904 38.5FM(n,f)144Ce 284.91 (5) d 133.515 11.09 E NTR, TR E704, E70580.120 1.36407 (2-5, 28-30)(see Table 2)FM(n,f)140Ba 12.7527 (23) d 537.261 24.439 E NTR, TR E393, E704,(see Table 2) E705140Ba140La 1.67855 (12) d 1596.21 95.4 (2-5, 28-30)815.772 23.2776487.021 45.5058(see
45、Table 2)FM(n,f)137Cs 30.05 (8) a 661.657 84.99 E NTR, TR E704,(see Table 2) E705137Cs137mBa 2.552 (1) min 661.657 89.90 (2-5, 28-30)(see Table 2)FM(n,f)106Ru 371.8 (18) d E NTR, TR E704, E705(see Table 2) (2-5, 28-30)106Ru106Rh 30.07 (35) s 511.8605 20.4(see Table 2)FM(n,f)103Ru 39.26 (2) d 497.085
46、91.0 E NTR, TR E704, E705(see Table 2) (2-5, 28-30)FM(n,f)95Zr 64.032 (6) d 756.725 54.38 E NTR, TR E704, E705724.192 44.27 (2-5, 28-30)(see Table 2)95Zr95Nb 34.991 (6) d 765.803 99.808(see Table 2)A The numbers in parentheses following some given values is the uncertainty in the last digit(s) of th
47、e value: 0.729 (8) means 0.729 0.008, 70.8 (1) means 70.8 0.1.B NTR = Non-Threshold Response, TR = Threshold Response.C The time units listed for half-life are years (a), days (d), hours (h), minutes (min), and seconds (s). Note that a “year” herein is considered to be tropical and equivalentto 365.
48、242 days and thus equivalent to 31.556.926 s per Ref (31).D The nuclear data has been drawn from several primary sources including Refs (31-34). Reference (35) summarizes the source of the selected nuclearconstants.constants, last checked for consistency on March 19, 2014.E FM = Fission Monitor: 235
49、U and 239Pu (NTR) and 238U, 237Np, and 232Th (TR) target isotope or weight fraction varies with material batch.E1005 164E2956 Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels2.3 ANSI Standard:N42.14 Calibration and Usage of Germanium Detectors for Measurement of Gamma-Ray Emission Rates of Radionuclides53. Terminology3.1 Definitions:3.1.1 radiometric monitor (RM), dosimeter, foila small quantity of material consisting of or containing an accurately knownmass of a specific target nuclide. Usually fabricated
