E185 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

E261 Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

E263 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron

E264 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel

E265 Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32

E266 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum

E393 Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters

E482 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

E523 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper

E526 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium

E531 Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials

E704 Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238

E705 Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237

E720 Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics

E721 Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics

E722 Standard Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation-Hardness Testing of Electronics

E853 Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results

E854 Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)

E910 Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

E944 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)

E1005 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance

E1006 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments

E1018 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)

E1035 Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

E1297 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

E1854 Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts

E1855 Standard Test Method for Use of 2N2222A Silicon Bipolar Transistors as Neutron Spectrum Sensors and Displacement Damage Monitors

E2006 Standard Guide for Benchmark Testing of Light Water Reactor Calculations

E2956 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels

E170 Terminology Relating to Radiation Measurements and Dosimetry

E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)

E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706 (IIIA)

E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)

E1214 Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)

E2005 Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields

E2006 Guide for Benchmark Testing of Light Water Reactor Calculations