ANS 57.9-1992 (R2000)
Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type)
standard by American Nuclear Society, 01/01/1992
Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type)
standard by American Nuclear Society, 01/01/1992
Determination of Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
standard by American Nuclear Society, 09/16/2005
Safety in Conducting Subcritical Neutron-Multiplication Measurements in Situ
standard by American Nuclear Society, 05/16/1983
Determining Meteorological Information at Nuclear Facilities
standard by American Nuclear Society, 01/01/2000
Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
standard by American Nuclear Society, 02/11/1999
Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations
standard by American Nuclear Society, 03/16/2007
Criteria for Nuclear Criticality Safety Conrols in Operations With Shielding and Confinement
standard by American Nuclear Society, 09/14/1983
Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors
standard by American Nuclear Society, 09/09/1998
Determining Meteorological Information at Nuclear Facilities
standard by American Nuclear Society, 08/20/2015