ASTM E531-76(1996)e1 - 26.3.1976
 
1. Scope

1.1 This practice covers procedures for specimen testing to establish changes occurring in the mechanical properties due to irradiation and thermal effects of nuclear component metallic materials where these materials are used for high temperature applications above 370°C (700°F).

 
2. Referenced Documents

E844-18

Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance

E2006-22

Standard Guide for Benchmark Testing of Light Water Reactor Calculations

E261-16(2021)

Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

E185-21

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

E29-22

Standard Practice for Using Significant Digits in Test Data to Determine Conformance with Specifications

E23-23a

Standard Test Methods for Notched Bar Impact Testing of Metallic Materials (Includes all amendments and changes 4/13/2023).

E21-20

Standard Test Methods for Elevated Temperature Tension Tests of Metallic Materials

E8/E8M-24

Standard Test Methods for Tension Testing of Metallic Materials

E453-79(2001)

Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties (Withdrawn 2008)

E139-11(2018)

Standard Test Methods for Conducting Creep, Creep-Rupture, and Stress-Rupture Tests of Metallic Materials

E112-13(2021)

Standard Test Methods for Determining Average Grain Size

E45-18a(2023)

Standard Test Methods for Determining the Inclusion Content of Steel (Includes all amendments and changes 11/6/2023).

E3-11(2017)

Standard Guide for Preparation of Metallographic Specimens

A370-23

Standard Test Methods and Definitions for Mechanical Testing of Steel Products

E606-04

Standard Practice for Strain-Controlled Fatigue Testing

E482-22

Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

E468-18

Standard Practice for Presentation of Constant Amplitude Fatigue Test Results for Metallic Materials

E2215-19

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

E1823-23

Standard Terminology Relating to Fatigue and Fracture Testing

E647-23a

Standard Test Method for Measurement of Fatigue Crack Growth Rates (Includes all amendments and changes 6/27/2023).