Standard Practice for Calculation of Absorbed Dose from Neutron Irradiation by Application of Threshold-Foil Measurement Data
|Publication Date:||15 May 1991|
1.1 Radiation effects test results can be correlated to the absorbed dose in the material being tested. This practice outlines a procedure for calculating the absorbed dose in a material given the following information: the material composition, the neutron fluence, and threshold-foil data related to the neutron spectrum. This practice can also be used to calculate that fraction of the total absorbed dose in silicon caused by displacements (see Practice E 722). This quantity can be used to correlate the relative permanent damage in silicon semiconductor devices from one test facility to another. The practice is applicable to fast-pulsed-reactors
1.2 To the greatest extent practical, the international system of units (SI) is used throughout this practice (see Practice E 380). The values stated in SI units are to be regarded as the standard.
1.3 This standard does not purport to address all of the safety problems, 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.