1.1 This practice covers the evaluation of test specimens and dosimetry from light water moderated nuclear power reactor pressure vessel surveillance capsules.
1.2 Additionally, this practice provides guidance on reassessing withdrawal schedule for design life and operation beyond design life.
1.3 This practice is one of a series of standard practices that outline the surveillance program required for nuclear reactor pressure vessels. The surveillance program monitors the irradiation-induced changes in the ferritic steels that comprise the beltline of a light-water moderated nuclear reactor pressure vessel.
1.4 This practice along with its companion surveillance program practice, Practice E185, is intended for application in monitoring the properties of beltline materials in any lightwater moderated nuclear reactor.2
1.5 Modifications to the standard test program and supplemental tests are described in Guide E636.
1.6 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
ASTM E2215-16 Referenced Document
ASTM A370 Standard Test Methods and Definitions for Mechanical Testing 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 E185 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
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 E23 Standard Test Methods for Notched Bar Impact Testing of Metallic Materials
ASTM E509 Standard Guide for In-Service Annealing of Light-Water Cooled Nuclear Reactor Vessels
ASTM E636 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
ASTM E693 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706(ID)
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 E2215-16 history
2019ASTM E2215-19 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
2018ASTM E2215-18 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
2016ASTM E2215-16 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
2015ASTM E2215-15 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
2010ASTM E2215-10 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
2002ASTM E2215-02 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels