ASTM E1005-2015 red 5625 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance《反应堆压力容器监测用辐射监测器的应用和分析的标准试验方法》.pdf

1、Designation: E1005 10E1005 15Standard Test Method forApplication and Analysis of Radiometric Monitors forReactor Vessel Surveillance, E 706 (IIIA)Surveillance1This standard is issued under the fixed designation E1005; the number immediately following the designation indicates the year oforiginal ado

2、ption 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 describes general procedures for measuring the specifi

3、c activities of radioactive nuclides produced inradiometric monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures.More detailed procedures for individual RMs are provided in separate standards identified in 2.1 and in Refs 1, (2-1-5.).2

4、Themeasurement results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterizethe irradiation environment of the reactor vessel and support structure. The principal measurement technique is high resolutiongamma-ray spectrometry, although X-ray phot

5、on spectrometry and Beta particle counting are used to a lesser degree for specificRMs (6-1-29).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,

6、 self absorption of radiation by the RM,other absorption effects, radioactive decay corrections, and burn out of the nuclide of interest (6-1526, 16-26).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

7、of the irradiation, the half life, the mass of the 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 (2-530,28-30).1.1

8、.3 Procedures for calculation of reaction rates from 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 ot

9、her reaction rates can be used to define the neutron spectrum through the use ofsuitable computer programs (2-530,28-30).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,

10、required for calculation of absolute reaction rates 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 environ

11、ments and the certifiedbenchmark fluence rate (2-530,28-30).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 s

12、tructuresurveillance measurements:E706 Master Matrix 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 Te

13、rms of Displacements Per Atom (DPA),E706 (ID)3E185 Practice 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

14、Surveillance Tests for Nuclear Power Reactor Vessels, 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 Se

15、ction and Data File, E706 (IIB)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 Jan. 1, 2010July 1, 2015. Published February 2010Oc

16、tober 2015. Originally approved in 1997. Last previous edition approved in 20032010 asE10050310.1. DOI: 10.1520/E1005-10.10.1520/E1005-15.2 The boldface numbers in parentheses refer to the list of references appended to this method.3 The reference in parentheses refers to Section 5 as well as Figs.

17、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 depict all changes accurately, ASTM recommends that

18、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 19428-2959. United States1E482 Guide for Applicatio

19、n of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)3E2005 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

20、 Solid State Track Recorder (SSTR) Monitors for 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 Surveill

21、ance, E706 (IIIE) 31.3 The general procedures in this test 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, 2-1-5 (s

22、ee Table 1).1.4 This test method, along with the individual RM 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 value

23、s stated in SI units are to be regarded as standard. No other units of measurement are included in thisstandard.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 addres

24、s all of the safety concerns, if any, associated with its use. It is the 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 ident

25、ified in 1.2), including those for individual RM monitors:2.2 ASTM Standards: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

26、, Fluence Rate, and Spectra by Radioactivation TechniquesE262 Test Method 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 F

27、ast-Neutron Reaction Rates by Radioactivation of NickelE265 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32E266 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of AluminumE320 Test Method for Cesium-137 in Nuclear Fuel Solut

28、ions by Radiochemical Analysis (Withdrawn 1993)5E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission DosimetersE481 Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and SilverE482 Guide for Application of Neutron Transport Methods for React

29、or Vessel Surveillance, E706 (IID)E523 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of CopperE526 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of TitaniumE636 Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessel

30、s, 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 Rates by Radioactivation of Uranium-238E705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-

31、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 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance,E706(

32、IIIB)E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel MaterialsE910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,E706 (IIIC)E944 Guide for Application of Neutron Spectrum Adjustment Methods

33、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 Nuclear Reactor Vessel Support Structures4 For referencedASTM standards, visit theASTM website, www.astm.org, or contactAST

34、M Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.E1005 152TABLE 1 Radiometric Monitors Proposed for Reactor Vessel SurveillanceDosimetryReactionsResidual NucleusTarget Atom NaturalAbundanceA 3

35、1DetectorResponseBASTMStandard orRef.RefHalf-lifeC,A,D ED(keV)YieldD(%)/Reaction23Na(n,)24Na 0.62356 (17) d 1368.633 99.9936 1.00 NTR (2-30)23Na(n,)24Na 14.9574 (20) h 1368.626 99.9935 1.00 NTR (2-5,28-31)2754.030 99.8552754.007 99.87227Al(n,)24Na 0.62356 (17) d 1368.633 99.9936 1.00 TR E26627Al(n,)

36、24Na 14.9574 (20) h 1368.626 99.9935 1.00 TR (31)E2662754.030 99.8552754.007 99.87232S(n,p)32P 14.262 (14) d =694.9 100. 0.9502 (9) TR E26532S(n,p)32P 14.284 (14) d =694.9 100. 0.9502 (9) TR E26545Sc(n,)46Sc 83.79 (4) d 889.277 99.9844 1.00 NTR (2-30)45Sc(n,)46Sc 83.788 (22) d 889.277 99.9844 1.00 N

37、TR (2-5,28-31)1120.545 99.987446Ti(n,p)46Sc 83.79 (4) d 889.277 99.9844 0.0825 (3) TR E52646Ti(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 (1) d 159.381 68.3 0.0744 (2) TR E52647Ti(n,p)47Sc 3.3492 (6) d 159.381 68.3 0.0744 (2) TR E52648Ti(n,p)48

38、Sc 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, E26355Mn(n,2n)54Mn 312.13 (3) d 834.838 99.9758 1.00 TR E261, E263(2-30)(2-5,28-30)54Fe(n,p)54Mn 312.11 (5) d 834.843 99.9758 0.05845 (35) TR E26354Fe(n,p)54Mn 312.13 (

39、3) d 834.838 99.9758 0.05845 (35) TR E26354Fe(n,)55Fe 2.73 (3) y 5.888 8.2 0.05845 (35) NTR (2-30)54Fe(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 2.5789 (1) hr 846.754 98.87 0.91754 (36) TR (2-30)56Fe(n,p)56Mn 2.57878 (46) h 846.764 98.85 0.91754 (36)

40、 TR (2-5,28-30)1810.72 27.189251810.73 26.88722113.05 14.336152113.09 14.234458Fe(n,)59Fe 44.472 (8) d 1099.251 56.5 0.00282 (4) NTR (2-30)58Fe(n,)59Fe 44.495 (9) d 1099.245 56.5 0.00282 (4) NTR (2-5,28-30)1291.596 43.21291.590 43.21481.7 0.05959Co(n,)60Co 1925.5 (5) d 1173.238 99.857 1.00 NTR E262,

41、 E48159Co(n,)60Co 1925.28 (14) d 1173.228 99.85 1.00 NTR E262, E4811332.502 99.9831332.492 99.982610.467 (6) m 58.603 2.0110.467 (6) min 58.603 2.07(meta) 826.28 0.00768(meta) 826.10 0.007751332.501 0.241332.492 0.252158.77 0.000722158.57 0.0007558Ni(n,p)58Co 70.82 (3) d 810.775 99.45 0.68077 (9) TR

42、 E26458Ni(n,p)58Co 70.86 (6) d 810.7593 99.45 0.68077 (9) TR E264863.959 0.69863.951 0.691674.730 0.519E1005 153TABLE 1 ContinuedDosimetryReactionsResidual NucleusTarget Atom NaturalAbundanceA 31DetectorResponseBASTMStandard orRef.RefHalf-lifeC,A,D ED(keV)YieldD(%)/Reaction1674.725 0.5079.15 (10) h

43、(meta) 24.889 0.03699.10 (9) h (meta) 24.889 0.039760Ni(n,p)60Co 1925.5 (5) d 1173.238 99.857 0.26223 (8) TR (2-30)60Ni(n,p)60Co 1925.28 (14) d 1173.238 99.85 0.26223 (8) TR (2-5,28-30)1332.502 99.9831332.492 99.982610.467 (6) m 58.603 2.0110.467 (6) m 58.603 2.07(meta) 826.28 0.00768(meta) 826.10 0

44、.007751332.501 0.241332.492 0.252158.77 0.000722158.57 0.0007563Cu(n,)64Cu 12.700 (2) h 1345.77 0.47336 0.6917 (3) NTR (2-30)63Cu(n,)64Cu 12.701 (2) h 1345.77 0.475395 0.6917 (3) NTR (2-5,28-30)63Cu(n,)60Co 1925.5 (5) d 1173.238 99.857 0.6917 (3) TR E52363Cu(n,)60Co 1925.28 (14) d 1173.238 99.85 0.6

45、917 (3) TR E5231332.502 99.9831332.492 99.982610.467 (6) m 58.603 2.0110.467 (6) min 58.603 2.07(meta) 826.33 0.0058(meta) 826.10 0.007751332.501 0.251332.492 0.252158.86 0.000882158.57 0.0007593Nb(n,n)93mNb 5.89 (5) 103 d 30.77 0.000549 1.00 TR (1,2-30)93Nb(n,n)93mNb 5.89 (5) 103 d 30.77 0.000591 1

46、.00 TR (1-5,28-30)16.52 (K1,2) 9.25103Rh(n,n)103mRh 56.114 (9) m 39.755 0.0684 1.00 TR (2-30)103Rh(n,n)103mRh 56.114 (20) min 39.755 0.0684 1.00 TR (2-5,28-30)109Ag(n,)110mAg 249.76 (4) d 116.48 0.00799 0.48161 (8) NTR E481109Ag(n,)110mAg 249.78 (2) d 116.48 0.00799 0.48161 (8) NTR E481884.685 72.19

47、2884.6781 74.0937.493 34.1314937.485 34.511384.300 24.12041384.2931 24.471505.040 12.95321505.028 13.161475.788 3.968681475.7792 4.03115ln(n,)116mln 54.29 (17) m 1293.54 84.4 0.9571 (5) NTR E261, E262115ln(n,)116mln 54.29 (17) min 1293.56 84.8 0.9571 (5) NTR E261, E2621097.3 56.21041097.28 58.512818

48、.7 11.4784818.68 12.1262112.1 15.52962112.19 15.094115ln(n,n)115mln 4.486 (4) h 336.241 45.9 0.9571 (5) TR (2-30)115ln(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 (3) d 1121.3008 34.9 0.99988 (2) NTR E262181Ta(n,)182Ta 114.74 (12) d 1121.290 35.24

49、0.9998799 (32) NTR E2621189.0503 16.2251189.040 16.4851221.4066 26.97771221.395 27.230E1005 154TABLE 1 ContinuedDosimetryReactionsResidual NucleusTarget Atom NaturalAbundanceA 31DetectorResponseBASTMStandard orRef.RefHalf-lifeC,A,D ED(keV)YieldD(%)/Reaction197Au(n,)198Au 2.69517 (21) d 1087.6904 0.159045 1.00 NTR E261, E262197Au(n,)198Au 2.69517 (21) d 1087.6842 0.159 1.00 NTR E261, E262675.8874 0.8038278 (2-30)675.8836 0.806 (2-5,28-30)411.804 95.57411.802504 95.54232Th(n,)233Th 22.3 (1) m 890.1 0.14 1.00 NTR (2-30)232Th(n,)233