ASTM E526-22

Standard Test Method for Measuring Fast-Neutron Reaction Rates By Radioactivation of Titanium

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NORMA vydána dne 1.7.2022


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DostupnostSKLADEM
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Informace o normě:

Označení normy: ASTM E526-22
Datum vydání normy: 1.7.2022
Kód zboží: NS-1069737
Počet stran: 5
Přibližná hmotnost: 15 g (0.03 liber)
Země: Americká technická norma
Kategorie: Technické normy ASTM

Kategorie - podobné normy:

Měření radiace
Štěpné materiály

Anotace textu normy ASTM E526-22 :

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)

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. Scope

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.

Note 1:?The 47Ti(n,np)46Sc reaction, ENDF-6 format file/reaction identifier MF=3, MT=28, is distinguished from the 47Ti(n,d)46Sc reaction, ENDF-6 format file/reaction identifier MF=3/MT=104, even though it leads to the same residual product (1).2 The combined reaction, in the IRDFF-II library, has the file/reaction identifier MF=10/MT=5.

Note 2:?The cross section for the combined 47Ti(n,np:d) reaction is relatively small for energies less than 12 MeV and, in fission reactor spectra, the production of the residual 46Sc is not easily distinguished from that due to the 46Ti(n,p) reaction.

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.

  2. Referenced Documents

E261-16(2021)

Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

E170-23

Standard Terminology Relating to Radiation Measurements and Dosimetry

E181-23

Standard Guide for Detector Calibration and Analysis of Radionuclides in Radiation Metrology for Reactor Dosimetry

E262-17

Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques

E844-18

Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance

E1018-20e1

Standard Guide for Application of ASTM Evaluated Cross Section Data File (Includes all amendments and changes 7/2/2020).

E944-19

Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance

E1005-21

Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance

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