Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plantsstandard by American Nuclear Society, 12/12/1989

Nuclear Criticality Safety Trainingstandard by American Nuclear Society, 05/20/1991

Radioactive Source Term for Normal Operation of Light Water Reactorsstandard by American Nuclear Society, 11/01/2016

Fuel Assembly Identificationstandard by American Nuclear Society, 11/08/1978

Portability of Scientific and Engineering Softwarestandard by American Nuclear Society, 12/20/2000

Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactorsstandard by American Nuclear Society, 09/11/1987

Time Response Design Criteria for Safety Related Operator Actionsstandard by American Nuclear Society, 08/23/1994

Subcompartment Pressure and Temperature Transient Analysis in Light Water Reactorsstandard by American Nuclear Society, 01/01/1982

Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactorsstandard by American Nuclear Society, 09/25/1997

Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuelstandard by American Nuclear Society, 01/01/1982

The Development of Technical Specifications for Research Reactorsstandard by American Nuclear Society, 04/20/2007

Fuel-Oil Systems for Emergency Diesel Generatorsstandard by American Nuclear Society, 10/27/1989