Hello. Sign In
Standards Store

ANS 6.1.1

1991 Edition, January 1, 1991

Complete Document

Neutron and Gamma-Ray Fluence-to-Dose Factors

View Abstract
Product Details
Document History

Detail Summary

Not Active, See comments below

Additional Comments:
Price (USD)
Secure PDF
Single User
Call for Quote
Call for Quote
Add to Cart

Product Details:

  • Revision: 1991 Edition, January 1, 1991
  • Published Date: January 1991
  • Status: Not Active, See comments below
  • Document Language: English
  • Published By: American Nuclear Society (ANS)
  • Page Count: 26
  • ANSI Approved: Yes
  • DoD Adopted: No

Description / Abstract:

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.


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.