ASTM E531-13

Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials (Withdrawn 2022)

Automatically translated name:

Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials

STANDARD published on 1.1.2013

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The information about the standard:

Designation standards: ASTM E531-13
Note: WITHDRAWN
Publication date standards: 1.1.2013
SKU: NS-47111
The number of pages: 6
Approximate weight : 18 g (0.04 lbs)
Country: American technical standard
Category: Technical standards ASTM

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The category - similar standards:

Reactor engineering

Annotation of standard text ASTM E531-13 :

Keywords:
irradiation, nuclear reactor vessels (high temperature), radiation exposure, surveillance (of nuclear reactor vessels), ICS Number Code 27.120.10 (Reactor engineering)

Additional information

Significance and Use

4.1 The requirements contained herein can be used as a basis for establishing conditions for safe operation of critical components. The requirements provide for general plant assessment and verification that materials meet design criteria. The test specimens and procedures presented in this practice are for guidance when establishing a surveillance program.

4.2 This practice for high-temperature materials surveillance programs is used when nuclear reactor component materials are monitored by specimen testing. Periodic testing is performed through the service life of the components to assess changes in selected material properties that are caused by neutron irradiation and thermal effects. The properties are those used as design criteria for the respective nuclear components. The extent of material property change caused by neutron irradiation depends on the composition and structure of the initial material, its conditioning in component fabrication, as well as the nature of the irradiation exposure. The need for surveillance arises from a concern of specific material behavior under all irradiation conditions including spectrum and rate effects on material properties.

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).

1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

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).