ASTM E706-16
Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards

Standard No.

ASTM E706-16

Release Date

2016

Published By

American Society for Testing and Materials (ASTM)

Status

Be replaced

Replace By

ASTM E706-23

Latest

ASTM E706-23

Scope

1.1 This master matrix standard describes a series of standard practices, guides, and methods for the prediction of neutron-induced changes in light-water reactor (LWR) pressure vessel (PV) and support structure steels throughout a pressure vessel’s service life (Fig. 1). Referenced documents are listed in Section 2. The summary information that is provided in Sections 3 and 4 is essential for establishing proper understanding and communications between the writers and users of this set of matrix standards. It was extracted from the referenced standards (Section 2) and references for use by individual writers and users. More detailed writers’ and users’ information, justification, and specific requirements for the individual practices, guides, and methods are provided in Sections 3 – 5. General requirements of content and consistency are discussed in Section 6. 1.2 This master matrix is intended as a reference and guide to the preparation, revision, and use of standards in the series. 1.3 To account for neutron radiation damage in setting pressure-temperature limits and making fracture analyses (112)2 and Guide E509), neutron-induced changes in reactor pressure vessel steel fracture toughness must be predicted, then checked by extrapolation of surveillance program data during a vessel’s service life. Uncertainties in the predicting methodology can be significant. Techniques, variables, and uncertainties associated with the physical measurements of PV and support structure steel property changes are not considered in this master matrix, but elsewhere (2, 6, 7), (11-26), and Guide E509). 1.4 The techniques, variables and uncertainties related to (1) neutron and gamma dosimetry, (2) physics (neutronics and gamma effects), and (3) metallurgical damage correlation procedures and data are addressed in separate standards belonging to this master matrix (1, 17). The main variables of concern to (1), (2), and (3) are as follows: 1.4.1 Steel chemical composition and microstructure, 1.4.2 Steel irradiation temperature, 1.4.3 Power plant configurations and dimensions, from the core periphery to surveillance positions and into the vessel and cavity walls. 1.4.4 Core power distribution, 1.4.5 Reactor operating history, 1.4.6 Reactor physics computations, 1.4.7 Selection of neutron exposure units, 1.4.8 Dosimetry measurements, 1.4.9 Neutron special effects, and 1.4.10 Neutron dose rate effects. 1.5 A number of methods and standards exist for ensuring the adequacy of fracture control of reactor pressure vessel belt lines under normal and accident loads ((1, 7, 8, 11, 12, 14, 16, 17, 23-27), Referenced Documents: ASTM Standards (2.1), Nuclear Regulatory Documents (2.3) and ASME Standards (2.4)). As older LWR pressure vessels become more highly irradiated, the predictive capability for changes in toughness must improve. Since during a vessel’s service life an increasing amount of information will be available from test reactor and power reactor surveillance programs, procedures to evaluate and use this information must be used (1, 2, 4-9, 11, 12, 23-26, 28). This master matrix defines the current (1) scope, (2) areas of application, and (3) general grouping for the series of ASTM standards, as shown in Fig. 1. 1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the 1 This practice is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05 on Nuclear Radiation Metrology. Current edition approved Dec. 1, 2016. Published January 2017. Originally approved in 1979. Last previous edition approved in 2002 as E0706 -2002 which was withdrawn July 2011 and reinstated in December 2016. DOI: 10.1520/E070616. 2 The boldface numbers in parentheses refer to a list of references at the end of this standard. Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. 1 responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ASTM E706-16 Referenced Document

• ASTM C859 Standard Terminology Relating to Nuclear Materials
• ASTM E1005 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
• ASTM E1006 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
• ASTM E1018 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
• ASTM E1035 Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
• 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 E185 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
• ASTM E2005 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
• ASTM E2006 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
• ASTM E2215 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels*， 2019-06-01 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 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 E646 Standard Test Method for Tensile Strain-Hardening Exponents (n -Values) of Metallic Sheet Materials*， 2024-04-22 Update
• ASTM E693 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706(ID)
• 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 E854 Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)
• ASTM E900 Standard Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, E 706 (IIF)
• ASTM E910 Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)
• ASTM E944 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)

ASTM E706-16 history

• 2023 ASTM E706-23 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
• 2016 ASTM E706-16 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
• 2002 ASTM E706-02 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)
• 2001 ASTM E706-01 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)
• 1987 ASTM E706-87(1994) Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)