ASTM E706-23
Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
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ASTM E706-23
Standard No.
ASTM E706-23
Release Date
2023
Published By
American Society for Testing and Materials (ASTM)
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 responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.8 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 This master matrix 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 March 1, 2023. Published March 2023. Originally approved in 1979. Last previous edition approved in 2016 as E706 – 16. DOI: 10.1520/E0706-23. 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 2. Referenced Documents
ASTM E706-23 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
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
*
,
2024-04-21 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 E706-23 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)
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