ASTM E266-02 - 10.6.2002
 
1. Scope

1.1 This test method covers procedures measuring reaction rates by the activation reaction 7Al(n,alpha)24Na.

1.2 This activation reaction is useful for measuring neutrons with energies above approximately 6.5 MeV and for irradiation times up to about 2 days (for longer irradiations, see Practice E 261).

1.3 With suitable techniques, fission-neutron fluence rates above 106cm-2·s-1 can be determined.

1.4 Detailed procedures for other fast neutron detectors are referenced in Practice E 261.

1.5 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 and health practices and determine the applicability of regulatory limitations prior to use.

 
2. Referenced Documents

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

E261-16(2021)

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

E844-18

Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance

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

E1018-20e1

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