Category: ANS

Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments
standard by American Nuclear Society, 04/16/2020

Auxiliary Feedwater System for Pressurized Water Reactors
standard by American Nuclear Society, 10/23/2020

Determining Design Basis Flooding at Power Reactor Sites
standard by American Nuclear Society, 01/01/1992

Auxiliary Feedwater System for Pressurized Water Reactors
standard by American Nuclear Society, 05/10/1991

standard by American Nuclear Society, 2016

Standard for Radiological Accident Offsite Consequence Analysis (Level 3 PRA) to Support Nuclear Installation Applications – ASME/ANS RA-S-1.3-2017 (Trial Use Standard)
standard by American Nuclear Society, 07/13/2017

Determining Meteorological Information at Nuclear Facilities
standard by American Nuclear Society, 01/01/2000

Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type)
standard by American Nuclear Society, 01/01/1992

Design Basis for Protection of Light Water Nuclear Power Plants Against the Effects of Postulated Pipe Rupture
standard by American Nuclear Society, 01/01/1988

Steady-state Neutronics Methods for Power Reactor Analysis
standard by American Nuclear Society, 08/26/2011