ASTM E693 - 12e1 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
Citing ASTM Standards Citation data is made available by participants in CrossRefs Cited-by Linking service. A comprehensive list of citations to this standard are listed here.
E261 Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E482 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
E706 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
E722 Standard Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation-Hardness Testing of Electronics
E900 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
E944 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
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
E1035 Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
E2215 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
E2956 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
Referenced ASTM Standards The documents listed below are referenced within the subject standard but are not provided as part of the standard.
E170 Terminology Relating to Radiation Measurements and Dosimetry
E521 Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation
E821 Practice for Measurement of Mechanical Properties During Charged-Particle Irradiation
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)