6.1.1-1991

Neutron and Gamma-Ray Fluence-to-Dose Factors

6.1.1-1991 发布历史

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.

6.1.1-1991由ANS - American Nuclear Society 发布于 1991-01-01，并于 2002-11-07 实施。

6.1.1-1991的历代版本如下：

• 1977年03月17日 6.1.1-1977
• 1991年01月01日 6.1.1-1991

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标准号

6.1.1-1991

发布日期

1991年01月01日

实施日期

2002年11月07日

废止日期

无

中国标准分类号

/

国际标准分类号

/

发布单位

ANS - American Nuclear Society

引用标准

26

适用范围

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.