ASTM E900 - 15 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials


    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.

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

    E509/E509M Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels

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

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

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

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

    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.

    A302 Specification for Pressure Vessel Plates, Alloy Steel, Manganese-Molybdenum and Manganese-Molybdenum-Nickel

    A508 Specification for Quenched and Tempered Vacuum-Treated Carbon and Alloy Steel Forgings for Pressure Vessels

    A533 Specification for Pressure Vessel Plates, Alloy Steel, Quenched and Tempered, Manganese-Molybdenum and Manganese-Molybdenum-Nickel

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

    E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)

    E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E 706(ID)

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

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

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

    E2215 Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels