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ASTM E 706 : 2016

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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

Available format(s)

Hardcopy , PDF

Superseded date

06-04-2023

Language(s)

English

Published date

24-01-2017

CONTAINED IN VOL. 12.02, 2017 Specifies 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.

1.1This 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.

1.2This master matrix is intended as a reference and guide to the preparation, revision, and use of standards in the series.

1.3To account for neutron radiation damage in setting pressure-temperature limits and making fracture analyses (1-12)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).

1.4The 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:

1.4.1Steel chemical composition and microstructure,

1.4.2Steel irradiation temperature,

1.4.3Power plant configurations and dimensions, from the core periphery to surveillance positions and into the vessel and cavity walls.

1.4.4Core power distribution,

1.4.5Reactor operating history,

1.4.6Reactor physics computations,

1.4.7Selection of neutron exposure units,

1.4.8Dosimetry measurements,

1.4.9Neutron special effects, and

1.4.10Neutron 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.

1.6The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

1.7This 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 and health practices and determine the applicability of regulatory limitations prior to use.

Committee
E 10
DocumentType
Standard
Pages
14
PublisherName
American Society for Testing and Materials
Status
Superseded
SupersededBy
Supersedes

ASTM E 482 : 2016 : REDLINE Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
ASTM E 1214 : 2011 : R2018 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
ASTM E 1214 : 2011 : R2023 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
ASTM E 944 : 2013-01 GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE
ASTM E 910 : 2018 : REDLINE Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
ASTM E 560 : 2001 Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706(IC) (Withdrawn 2009)
ASTM E 1214 : 2011 : EDT 1 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
ASTM E 1214 : 2011 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)
ASTM E 942 : 2016 : REDLINE Standard Guide for Investigating the Effects of Helium in Irradiated Metals
ASTM E 2006 : 2016 : REDLINE Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 583 : 1987 Practice for Systematizing the Development of (ASTM) Voluntary Consensus Standards for the Solution of Nuclear and Other Complex Problems (Withdrawn 1995)
ASTM E 1006 : 2013 : REDLINE Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
ASTM E 942 : 2016 Standard Guide for Investigating the Effects of Helium in Irradiated Metals
ASTM E 2006 : 2022 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 944 : 2019 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
ASTM E 910 : 2018 Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
ASTM E 2059 : 2020 Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
ASTM E 1006 : 2021 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
ASTM E 853 : 2018 Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
ASTM E 482 : 2016 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

ASTM E 1005 : 2010 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
ASTM E 1253 : 2007 Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
ASTM E 185 : 1998 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
ASTM E 693 : 2023 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
ASTM E 2006 : 2022 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM C 859 : 2023 Standard Terminology Relating to Nuclear Materials
ASTM E 1035 : 2013 Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
ASTM E 482 : 2016 : REDLINE Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
ASTM E 2005:2010 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 693 : 2017 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
ASTM C 859 : 2014 : REV B Standard Terminology Relating to Nuclear Materials
ASTM E 2956 : 2014 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
ASTM E 2005 : 2010 : R2015 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 1005 : 2015 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
ASTM E 2005 : 2005 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 693 : 2017 : REDLINE Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
ASTM E 482 : 2016 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
ASTM E 1253 : 2021 Standard Guide for Reconstitution of Charpy-Sized Specimens
ASTM E 1035 : 1985 : R1990 Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
ASTM E 1035 : 2018 Standard Practice for Determining Neutron Exposures for Nuclear Reactor<brk/> Vessel Support Structures
ASTM E 2005 : 1999 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 2956 : 2021 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
ASTM E 2215 : 2015 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 900 : 2015 : EDT 2 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
ASTM E 1253 : 2013 : REDLINE Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
ASTM E 170 : 2020 Standard Terminology Relating to Radiation Measurements and Dosimetry
ASTM E 944 : 1996 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)
ASTM E 1006 : 1996 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
ASTM E 2006 : 1999 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 2005 : 2005 : EDT 1 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 2215 : 2002 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 170 : 2017 : REDLINE Standard Terminology Relating to Radiation Measurements and Dosimetry
ASTM E 2215 : 2010 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 1006 : 2013 : REDLINE Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
ASTM E 170 : 2023 Standard Terminology Relating to Radiation Measurements and Dosimetry
ASTM E 2006 : 2005 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 2215 : 2016 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
ASTM C 859 : 2022 Standard Terminology Relating to Nuclear Materials
ASTM C 859 : 2022 : REV A Standard Terminology Relating to Nuclear Materials
ASTM E 2005 : 2021 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 1253 : 1999 Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
ASTM E 23 : 2002 Standard Test Methods for Notched Bar Impact Testing of Metallic Materials
ASTM E 1005 : 2021 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
ASTM E 854 : 2014-12 TEST METHOD FOR APPLICATION AND ANALYSIS OF SOLID STATE TRACK RECORDER (SSTR) MONITORS FOR REACTOR SURVEILLANCE
ASTM E 185 : 2016 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 1006 : 2013 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
ASTM E 2215 : 2019 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 1253 : 2013 Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
ASTM E 1005 : 2016 : REDLINE Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
ASTM E 2006 : 2016 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 1005 : 1997 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
ASTM E 2006 : 2016 : REDLINE Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 1005 : 2003 : EDT 1 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
ASTM E 900 : 2021 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
ASTM E 1035 : 2002 Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures
ASTM E 185 : 2021 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 185 : 2016 : REDLINE Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 2006 : 2010 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 1006 : 2002 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
ASTM E 1006 : 2008 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
ASTM E 2215 : 2018 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 1006 : 2021 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
ASTM E 1035 : 2008 Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures
ASTM E 1005 : 2016 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
ASTM E 1035 : 1985 : R1996 Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
ASTM E 944 : 2013-01 GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE
ASTM E 482 : 2022 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

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