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ANS - 6.1.2

Group-Averaged Neutron and Gamma-Ray Cross Sections for Radiation Protection and Shielding Calculations for Nuclear Power Plants

inactive
Organization: ANS
Publication Date: 1 January 2013
Status: inactive
Page Count: 18
scope:

This standard specifies group-averaged neutron and gamma-ray cross sections and related group-averaged or derived data for the energy range and materials of importance in radiation protection and shielding calculations for nuclear power plants.

Document History

ANS 6.1.2
January 1, 2013
Group-Averaged Neutron and Gamma-Ray Cross Sections for Radiation Protection and Shielding Calculations for Nuclear Power Plants
This standard specifies group-averaged neutron and gamma-ray cross sections and related group-averaged or derived data for the energy range and materials of importance in radiation protection and...
6.1.2
January 1, 2013
group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear power plants
This standard specifies group-averaged neutron and gamma-ray cross sections and related group-averaged or derived data for the energy range and materials of importance in radiation protection and...
6.1.2
January 1, 2013
Group-Averaged Neutron and Gamma-Ray Cross Sections for Radiation Protection and Shielding Calculations for Nuclear Power Plants
This standard specifies group-averaged neutron and gamma-ray cross sections and related group-averaged or derived data for the energy range and materials of importance in radiation protection and...
6.1.2
January 1, 1999
Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
A description is not available for this item.
6.1.2
January 1, 1999
Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
This standard specifies neutron amd gamma-ray cross sections and related group-avaraged or derived data for the energy range and materials of importance in nuclear radiation protection and shielding...
6.1.2
January 1, 1999
Neutron and Gamma-Ray Cross Sections for Radiation Protection Calculations for Nuclear Power Plants
This standard specifies neutron and gamma-ray cross sections and related group-averaged or derived data for the energy range and materials of importance in nuclear radiation protection and shielding...
6.1.2
January 1, 1989
Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
A description is not available for this item.
6.1.2
January 1, 1983
NEUTRON AND GAMMA-RAY CROSS SECTIONS FOR NUCLEAR RADIATION PROTECTION CALCULATIONS FOR NUCLEAR POWER PLANTS
A description is not available for this item.
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References

This document references:
ANS 19.1 - Nuclear Data Sets for Reactor Design Calculations
Published by ANS on January 1, 2019
General The purpose of this standard is to provide criteria for the use of nuclear data in reactor design calculations. Thus, this standard identifies and describes the specifications for developing,...
This document references:
ANS 19.3 - Steady-state neutronics methods for power reactor analysis
Published by ANS on January 1, 2011
This standard provides guidance for performing and validating the sequence of steady-state calculations leading to prediction—in all types of operating commercial nuclear reactors—of the following:...
This document references:
ANS 6.1.1 - Photon and Neutron Fluence-to-Dose Conversion Coefficients
Published by ANS on January 1, 2020
This standard1) presents data recommended for computing the biologically relevant dosimetric quantity in photon and neutron radiation fields. Specifically, this standard is intended for use by...
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