ASTM E185-16
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

Standard No.

ASTM E185-16

Release Date

2016

Published By

American Society for Testing and Materials (ASTM)

Status

Be replaced

Replace By

ASTM E185-21

Latest

ASTM E185-21

Scope

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 lightwater small modular reactor designs with a nominal design output of 300 MWe or less have not been specifically considered in this practice. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials. 1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) exceeds 1 × 1021 neutrons/m2 (1 × 1017 n/cm2 ) at the inside surface of the ferritic steel reactor vessel. 1.3 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the design life. Practice E2215 addresses changes to the withdrawal schedule during and beyond the design life. 1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. NOTE 1—The increased complexity of the requirements for a lightwater moderated nuclear power reactor vessel surveillance program has necessitated the separation of the requirements into three related standards. Practice E185 describes the minimum requirements for design of a surveillance program. Practice E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a reactor vessel. Guide E636 provides guidance for conducting additional mechanical tests. A summary of the many major revisions to Practice E185 since its original issuance is contained in Appendix X1. NOTE 2—This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. See Appendix X1.

ASTM E185-16 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, T_o, 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*， 2019-06-01 Update
• ASTM E2298 Standard Test Method for Instrumented Impact Testing of Metallic Materials*， 2018-06-01 Update
• 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 E185-16 history

• 2021 ASTM E185-21 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• 2016 ASTM E185-16 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• 2015 ASTM E185-15e1 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• 2015 ASTM E185-15 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• 2010 ASTM E185-10 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• 2002 ASTM E185-02 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• 1998 ASTM E185-98 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
• 1982 ASTM E185-82e2 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706 (IF)
• 1979 ASTM E185-79 Standard Practice for Conducting Surveillance Tests For Light-Water Cooled Nuclear Power Reactor Vessels
• 1973 ASTM E185-73 Standard Recommended Practice for Surveillance Tests For Nuclear Reactor Vessels