ASTM E266-07
Historical Standard: ASTM E266-07 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
SUPERSEDED (see Active link, below)
ASTM E266
1. Scope
1.1 This test method covers procedures measuring reaction rates by the activation reaction 27 Al(n,) 24 Na.
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 10 6 cm 2 s 1 can be determined.
1.4 Detailed procedures for other fast neutron detectors are referenced in Practice E 261.
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 (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
ASTM Standards
E170 Terminology Relating to Radiation Measurements and Dosimetry
E181 Test Methods for Detector Calibration and Analysis of Radionuclides
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706 (IIIA)
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)
Keywords
activation; activation reaction; aluminum; cross section; dosimetry; fast-neutron monitor; neutron metrology; pressure vessel surveillance; reaction rate; Neutron activation reactions; Radioactivation--fast neutron flux; Threshold detectors--6 MeV; Aluminum; Fast neutron flux/fluence ;
ICS Code
ICS Number Code 17.240 (Radiation measurements); 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/E0266-07
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