ASTM A302/A302M Standard Specification for Pressure Vessel Plates, Alloy Steel, Manganese-Molybdenum and Manganese-Molybdenum-Nickel
ASTM A508/A508M Standard Specification for Quenched and Tempered Vacuum-Treated Carbon and Alloy Steel Forgings for Pressure Vessels
ASTM A533/A533M Standard Specification for Pressure Vessel Plates, Alloy Steel, Quenched and Tempered, Manganese-Molybdenum and Manganese-Molybdenum-Nickel
ASTM E1005 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
ASTM E185 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
ASTM E2215 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels*, 2019-06-01 Update
ASTM E482 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
ASTM E693 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706(ID)
ASTM E853 Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)
ASTM E944 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)
ASTM E900-15e1 history
2021ASTM E900-21 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
2015ASTM E900-15e2 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
2015ASTM E900-15e1 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
2015ASTM E900-15 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
2002ASTM E900-02(2007) Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
2002ASTM E900-02 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
1987ASTM E900-87(2001) Standard Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, E 706 (IIF)
1987ASTM E900-87(1994) Standard Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, E 706 (IIF)