1.1?This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. New advanced light-water small modular reactor designs
ASTM E185-21 Referenced Document
ASTM A370 Standard Test Methods and Definitions for Mechanical Testing of Steel Products
ASTM A751 Standard Test Methods, Practices, and Terminology for Chemical Analysis of Steel Products
ASTM E1214 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E706(IIIE)
ASTM E1253 Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
ASTM E170 Standard Terminology Relating to Radiation Measurements and Dosimetry
ASTM E1820 Standard Test Method for Measurement of Fracture Toughness
ASTM E1921 Standard Test Method for Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range
ASTM E208 Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels
ASTM E21 Standard Test Methods for Elevated Temperature Tension Tests of Metallic Materials
ASTM E2215 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E2298 Standard Test Method for Instrumented Impact Testing of Metallic Materials
ASTM E23 Standard Test Methods for Notched Bar Impact Testing of Metallic Materials
ASTM E2956 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels*, 2023-09-01 Update
ASTM E482 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
ASTM E636 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
ASTM E8/E8M Standard Test Methods for Tension Testing of Metallic Materials*, 2024-01-01 Update
ASTM E844 Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)
ASTM E853 Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)
ASTM E900 Standard Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, E 706 (IIF)
ASTM E185-21 history
2021ASTM E185-21 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
2016ASTM E185-16 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
2015ASTM E185-15e1 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
2015ASTM E185-15 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
2010ASTM E185-10 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
2002ASTM E185-02 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
1998ASTM E185-98 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
1982ASTM E185-82e2 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706 (IF)
1979ASTM E185-79 Standard Practice for Conducting Surveillance Tests For Light-Water Cooled Nuclear Power Reactor Vessels
1973ASTM E185-73 Standard Recommended Practice for Surveillance Tests For Nuclear Reactor Vessels