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Standard Test Method for Measuring Fast-Neutron Reaction Rates By Radioactivation of Titanium
NORMA vydaná dňa 1.7.2022
Označenie normy: ASTM E526-22
Dátum vydania normy: 1.7.2022
Kód tovaru: NS-1069737
Počet strán: 5
Približná hmotnosť: 15 g (0.03 libier)
Krajina: Americká technická norma
Kategória: Technické normy ASTM
Keywords:
activation reaction, cross section, dosimetry, nuclear metrology, pressure vessel surveillance, reaction rate, titanium,, ICS Number Code 17.240 (Radiation measurements),27.120.30 (Fissile materials and nuclear fuel technology)
Significance and Use |
5.1?Refer to Guide E844 for the selection, irradiation, and quality control of neutron dosimeters. 5.2?Refer to Practice E261 for a general discussion of the determination of fast-neutron fluence rate with threshold detectors. 5.3?Titanium has good physical strength, is easily fabricated, has excellent corrosion resistance, has a melting temperature of 1668 ?C, and can be obtained with satisfactory purity. 5.4?46Sc has a half-life of 83.787 (16)5.5?The recommended representative isotopic abundances for natural titanium 8.25 (3) % 46Ti |
7.44 (2) % 47Ti |
73.72 (2) % 48Ti |
5.41 (2) % 49Ti |
5.18 (2) % 50Ti |
5.6?The radioactive products of the neutron reactions 47Ti(n,p)47Sc (?1/2 = 3.3485 (9) d) (2) and 48Ti(n,p)48Sc (?1/2 = 43.67 h), (3) might interfere with the analysis of 46Sc.
5.7?Contaminant activities (for example, 65Zn and 182Ta) might interfere with the analysis of 46Sc. See 7.1.2 and 7.1.3 for more details on the 182Ta and 65Zn interference.
5.8?46Ti and 46Sc have cross sections for thermal neutrons of 0.59 ? 0.18 and 8.0 ? 1.0 barns, respectively 5.9?Fig. 1 shows a plot of the International Reactor Dosimetry and Fusion File, IRDFF-II cross section FIG. 1?SAND-II 640-Group Histogram Representation of the natTi(n,X)46Sc Cross Section (Normalized per Elemental Ti Atom Using Natural Abundance Data), Represented By the Sum of the natTi(n,p)46Sc, natTi(n,np)46Sc, and natTi(n,d)46Sc Cross Section Components
FIG. 2?46Ti(n,p)46Sc Cross Section (Normalized per Isotopic 46Ti Atom), from IRDFF-II, with EXFOR Experimental Data
FIG. 3?47Ti(n,np:d)46Sc Cross Section (Normalized per Isotopic 47Ti Atom), from IRDFF-II, with EXFOR Experimental Data
1.1?This test method covers procedures for measuring reaction rates by the activation reaction natTi(n,X)46Sc. The X designation represents any combination of light particles associated with the production of the residual 46Sc product. Within the applicable neutron energy range for fission reactor applications, this reaction is a properly normalized combination of three different reaction channels: 46Ti(n,p)46Sc; 47Ti(n, np)46Sc; and 47Ti(n,d)46Sc.
1.2?The reaction is useful for measuring neutrons with energies above approximately 4.4 MeV and for irradiation times, under uniform power, up to about 250 days (for longer irradiations, or for varying power levels, see Practice E261).
1.3?With suitable techniques, fission-neutron fluence rates above 109 cm2?s1 can be determined. However, in the presence of a high thermal-neutron fluence rate, 46Sc depletion should be investigated.
1.4?Detailed procedures for other fast-neutron detectors are referenced in Practice E261.
1.5?The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
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.
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Standard Terminology Relating to Radiation Measurements and Dosimetry |
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Standard Guide for Detector Calibration and Analysis of Radionuclides in Radiation Metrology for Reactor Dosimetry |
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Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques |
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Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance |
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Standard Guide for Application of ASTM Evaluated Cross Section Data File (Includes all amendments and changes 7/2/2020). |
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Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance |
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Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance |
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