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ANS 6.1.1 1991 Edition, January 1, 1991
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Neutron and Gamma-Ray Fluence-to-Dose Factors
Additional Comments: W/D NO S/S
Page Count:26
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This standard presents data recommended for computing the biologically relevant dosimetric quantity in neutron and gamma-ray radiation fields. Specifically, this standard is intended for use by shield designers to calculate effective dose equivalent. Values are given for effective dose equivalent per unit fluence for neutron energies from 1 eV to 14 MeV and for gamma-ray energies from 0.01 to 12 MeV. Establishing maximum permissible exposure limits is outside the scope of this standard.

Purpose

The purpose of this standard is to assist those involved in the design or analysis of radiation facilities by providing the means to determine whether calculated fluence levels satisSr radiation exposure limits recommended by the International Commission on Radiological Protection (ICRP) or specified by regulatory agencies. The limits to which this standard is relevant are those intended to restrict the occurrence of stochastic, somatic effects to the individual to an acceptable level. Use of this standard in assessing the likelihood of nonstochastic effects, typically applications in which the dose equivalent is far in excess of occupational exposure guidelines, is not recommended, nor is this standard intended for use in testing or calibrating instruments.