ASTM E1005-21
Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance

Standard No.

ASTM E1005-21

Release Date

2021

Published By

American Society for Testing and Materials (ASTM)

Latest

ASTM E1005-21

Scope

1.1 This test method describes procedures for measuring the specific activities of radioactive nuclides produced in radiometric 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 (1-5).2 The measurement results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterize the irradiation environment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-ray spectrometry, although X-ray photon spectrometry and Beta particle counting 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 coincidence summing losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM, other 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 of count and the end of the irradiation, the half life, the mass of the target nuclide in the RM, and the branching intensities of the radiation of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be converted into corresponding reaction rates (2-5, 28-30). 1.1.3 Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history are included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section and effective irradiation time values, and, with other reaction rates can be used to define the neutron spectrum through the use of suitable 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 since many parameters, and their respective uncertainties, required for calculation of absolute reaction rates are common to both the benchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environment tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified benchmark fluence rate (2-5, 28-30). 1.2 This test method is intended to be used in conjunction with ASTM Guide E844 and existing or proposed ASTM practices, guides, and test methods that are also directly involved in the physics-dosimetry evaluation of reactor vessel and support structure surveillance measurements. 1.3 The procedures in this test method are applicable to the measurement of radioactivity in RMs that satisfy the specific constraints and conditions imposed for their analysis. More detailed procedures for individual RM monitors are identified in 2.1 and in Refs 1-5 (see Table 1). 1.4 This test method, along with the individual RM monitor standard methods, are intended for use by knowledgeable persons who are intimately familiar with the procedures, equipment, and techniques necessary to achieve high precision and accuracy in radioactivity measurements. 1.5 The values stated in SI units are to be regarded as standard. No other 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 the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. 1 This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05 on Nuclear Radiation Metrology. Current edition approved Sept. 1, 2021. Published November 2021. Originally approved in 1997. Last previous edition approved in 2016 as E1005 – 16. DOI: 10.1520/E1005-21. 2 The boldface numbers in parentheses refer to the list of references appended to this method. Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. 1 TABLE 1 Radiometric Monitors Proposed for Reactor Vessel Surveillance Dosimetry Reactions Residual Nucleus Target Atom Natural AbundanceA Ref (31) Detector ResponseB ASTM Standard or Ref Half-lifeC,A,D Eγ D (keV) YieldD (%) γ/Reaction 23 Na(n,γ)24 Na 14.958 (2) h 1368.630 (5) 99.9934 (5) 1.00 NTR (2-5, 28-32) 2754.049 (13) 99.862 (3) 27 Al(n,α)24 Na 14.958 (2) h 1368.630 (5) 99.9934 (5) 1.00 TR (32) E266 2754.049 (13) 99.862 (3) 32 S(n,p)32 P 14.284 (36) d =695.5 (3) 100.0 0.9499 (26) TR E265 45 Sc(n,γ)46 Sc 83.787 (16) d 889.271 (2) 99.98374 (25) 1.00 NTR (2-5, 28-32) 1120.537 (3) 99.97 (2) 46 Ti(n,p)46 Sc 83.787 (16) d 889.271 (2) 99.98374 (25) 0.0825 (3) NTR (32) E526 1120.537 (3) 99.97 (2) 47 Ti(n,p)47 Sc 3.3485 (9) d 159.373 (12) 68.1 (5) 0.0744 (2) TR E526 48 Ti(n,p)48 Sc 43.67 (9) h 983.526 (12) 100.0 (3) 0.7372 (3) TR E526 1037.522 (12) 97.5 (5) 1312.120 (12) 100.0 (5) 55 Mn(n,2n)54 Mn 312.19 (3) d 834.848 (3) 99.752 (5) 1.00 TR E261, E263 (2-5, 28-30) 54 Fe(n,p)54 Mn 312.19 (3) d 834.848 (3) 99.752 (3) 0.05845 (35) TR E263 54 Fe(n,γ)55 Fe 2.747 (8) a 5.88765 8.45 (14) 0.05845 (35) NTR (2-5, 28-30) 5.89875 16.57 (27) 6.49045 3.40 (7) 56 Fe(n,p)56 Mn 2.57878 (46) h 846.7638 (19) 98.85 (3) 0.91754 (36) TR (2-5, 28-30) 1810.726 (4) 26.9 (4) 2113.092 (6) 14.2 (3) 58 Fe(n,γ)59 Fe 44.494 (12) d 1099.245 (3) 56.51 (31) 0.00282 (4) NTR (2-5, 28-30) 1291.590 (6) 43.23 (33) 1481.70 (12) 0.059 (6) 59 Co(n,γ)60 Co 5.2711 (8) a 1173.228 (3) 99.85 (3) 1.00 NTR E262, E481 1332.492 (4) 99.9826 (6) 10.467 (6) min 58.603 (7) 2.07 (3) (meta) 826.10 (3) 0.00775 (3) 1332.492 (4) 0.25 (3) 2158.57 (3) 0.00075 (3) 58 Ni(n,p)58 Co 70.85 (3) d 810.7602 (20) 99.44 (2) 0.68077 (9) TR E264 863.958 (6) 0.700 (22) 1674.705 (6) 0.528 (13) 9.10 (9) h (meta) 24.889 (21) 0.0397 (6) 60 Ni(n,p)60 Co 5.2711 (8) a 1173.228 (3) 99.85 (3) 0.26223 (8) TR (2-5, 28-30) 1332.492 (4) 99.9826 (6) 10.467 (6) min 58.603 (7) 2.07 (3) (meta) 826.10 (3) 0.00775 (3) 1332.492 (4) 0.25 (3) 2158.57 (3) 0.00075 (3) 63 Cu(n,γ)64 Cu 12.7004 (20) h 1345.77 (6) 0.4748 (34) 0.6915 (15) NTR (2-5, 28-30) 63 Cu(n,α)60 Co 5.2711 (8) a 1173.228 (3) 99.85 (3) 0.6915 (15) TR E523 1332.492 (4) 99.9826 (6) 10.467 (6) min 58.603 (7) 2.07 (3) (meta) 826.10 (3) 0.00775 (3) 1332.492 (4) 0.25 (3) 2158.57 (3) 0.00075 (3) 93 Nb(n,n')93m Nb 16.12 (15) a 30.77 (2) 0.000591 (9) 1.00 TR (1-5, 28-30) 16.52 (Kα1,2) 9.25 103 Rh(n,n')103m Rh 56.114 (20) min 39.755 (12) 0.0684 (35) 1.00 TR (2-5, 28-30) 109 Ag(n,γ)110m Ag 249.78 (2) d 116.48 (5) 0.0080 (3) 0.48161 (8) NTR E481 884.6781 (13) 74.0 (12) E1005 − 21 2 TABLE 1 Continued Dosimetry Reactions Residual Nucleus Target Atom Natural AbundanceA Ref (31) Detector ResponseB ASTM Standard or Ref Half-lifeC,A,D Eγ D (keV) YieldD (%) γ/Reaction 937.485 (3) 34.51 (27) 1384.2931 (20) 24.7 (5) 1475.7792 (23) 4.03 (5) 1505.028 (2) 13.16 (16) 115 ln(n,γ)116m ln 54.29 (17) min 1293.56 (2) 84.8 0.9571 (5) NTR E261, E262 1097.28 (2) 58.512 818.68 (2) 12.126 2112.29 (2) 15.094 115 ln(n,n')115m ln 4.486 (4) h 336.241 (25) 45.9 (1) 0.9571 (5) TR (2-5, 28-30) 497.370 (29) 0.047 (1) 181 Ta(n,γ)182 Ta 114.61 (13) d 1121.290 (3) 35.17 (33) 0.9998799 (32) NTR E262 1189.040 (3) 16.58 (16) 1221.395 (3) 27.27 (27) 197 Au(n,γ)198 Au 2.6943 (3) d 1087.6842 (7) 0.1591 (21) 1.00 NTR E261, E262 675.8836 (7) 0.804 (5) (2-5, 28-30) 411.80205 (17) 95.62 (6) 232 Th(n,γ)233 Th 22.15 (8) min 890.1 (5) 0.1052 (14) 1.00 NTR (2-5, 28-30) 490.80 (6) 0.1078 (16) 499.02 (4) 0.1576 (21) 699.901 0.68 764.55 (6) 0.0891 (13) 233 Th⇒233 Pa 26.98 (2) d 311.904 (5) 38.3 (5) FM(n,f)144 Ce 284.89 (6) d 133.5152 (20) 10.83 (12) —E NTR, TR E704, E705 80.120 (4) 1.40 (5) (2-5, 28-30) (see Table 2) FM(n,f)140 Ba 12.753 (5) d 537.261 (25) 24.6 (5) —E NTR, TR E393, E704, (see Table 2) E705 140 Ba⇒140 La 1.67858 (21) d 1596.203 (13) 95.40 (5) (2-5, 28-30) 815.784 (6) 23.72 (20) 487.022 (6) 46.1 (5) (see Table 2) FM(n,f)137 Cs 30.05 (8) a 661.657 (3) 84.99 (20) —E NTR, TR E704, (see Table 2) E705 137 Cs⇒137m Ba 2.552 (1) min 661.657 (3) 90.07 (20) (2-5, 28-30) (see Table 2) FM(n,f)106 Ru 371.5 (21) d — — —E NTR, TR E704, E705 (see Table 2) (2-5, 28-30) 106 Ru⇒106 Rh 30.1 (3) s 511.8534 (23) 20.52 (23) (see Table 2) FM(n,f)103 Ru 39.247 (13) d 497.085 (10) 91.0 —E NTR, TR E704, E705 (see Table 2) (2-5, 28-30) FM(n,f)95 Zr 64.032 (6) d 756.729 (12) 54.38 (22) —E NTR, TR E704, E705 724.193 (3) 44.27 (22) (2-5, 28-30) (see Table 2) 95 Zr⇒95 Nb 34.991 (6) d 765.803 (6) 99.808 (7) (see Table 2) A The numbers in parentheses following some given values is the uncertainty in the last digit(s) of the 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 equivalent to 365.242 days and thus equivalent to 31.556.926 s per Ref (32). D The nuclear data has been drawn from several primary sources including Refs (32-35). Reference (36) summarizes the source of the selected nuclear constants, last checked for consistency on March 19, 2014. E FM = Fission Monitor: 235 U and 239 Pu (NTR) and 238 U, 237 Np, and 232 Th (TR) target isotope or weight fraction varies with material batch. E1005 − 21 3 2. Referenced Documents

ASTM E1005-21 Referenced Document

• ASTM E1018 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
• ASTM E1035 Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
• ASTM E1214 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E706(IIIE)
• ASTM E181 Standard Test Methods for Detector Calibration and Analysis of Radionuclides
• ASTM E185 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
• ASTM E2005 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
• ASTM E2006 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
• ASTM E261 Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• ASTM E262 Standard Method for Determining Thermal Neutron Reaction and Fluence Rates by Radioactivation Techniques
• ASTM E263 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
• ASTM E264 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
• ASTM E265 Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
• ASTM E266 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
• ASTM E2956 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels*， 2023-09-01 Update
• ASTM E393 Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
• ASTM E481 Standard Test Method for Measuring Neutron Fluence Rate by Radioactivation of Cobalt and Silver
• ASTM E482 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
• ASTM E523 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
• ASTM E526 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium
• ASTM E636 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
• ASTM E693 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706(ID)
• ASTM E704 Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
• ASTM E705 Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
• ASTM E844 Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)
• ASTM E853 Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)
• ASTM E854 Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)
• ASTM E900 Standard Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, E 706 (IIF)
• ASTM E910 Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)
• ASTM E944 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)

ASTM E1005-21 history

• 2021 ASTM E1005-21 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• 2016 ASTM E1005-16 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• 2015 ASTM E1005-15 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• 2010 ASTM E1005-10 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
• 2003 ASTM E1005-03e1 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
• 2003 ASTM E1005-03 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
• 1997 ASTM E1005-97 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)