ASTM E853-23
(Practice)Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
SIGNIFICANCE AND USE
3.1 The objectives of a reactor vessel surveillance program are twofold. The first requirement of the program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region resulting from exposure to neutron irradiation and the thermal environment. The second requirement is to make use of the data obtained from the surveillance program to determine the conditions under which the vessel can be operated throughout its service life.
3.1.1 To satisfy the first requirement of 3.1, the tasks to be carried out are straightforward. Each of the irradiation capsules that comprise the surveillance program may be treated as a separate experiment. The goal is to define and carry to completion a dosimetry program that will, a posteriori, describe the neutron field to which the material test specimens were exposed. The resultant information will then become part of a database applicable in a stricter sense to the specific plant from which the capsule was removed, but also in a broader sense to the industry as a whole.
3.1.2 To satisfy the second requirement of 3.1, the tasks to be carried out are somewhat complex. The objective is to describe accurately the neutron field to which the pressure vessel itself will be exposed over its service life. This description of the neutron field must include spatial gradients within the vessel wall. Therefore, heavy emphasis must be placed on the use of neutron transport techniques as well as on the choice of a design basis for the computations. Since a given surveillance capsule measurement, particularly one obtained early in plant life, is not necessarily representative of long-term reactor operation, a simple normalization of neutron transport calculations to dosimetry data from a given capsule may not be appropriate (1-67).
3.2 The objectives and requirements of a reactor vessel's support structure's surveillance program are much less stringent, and at present, are limited to ...
SCOPE
1.1 This practice covers the methodology, summarized in Annex A1, to be used in the analysis and interpretation of neutron exposure data obtained from LWR pressure vessel surveillance programs and, based on the results of that analysis, establishes a formalism to be used to evaluate present and future condition of the pressure vessel and its support structures2 (1-74).3
1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods (see Master Matrix E706) (1, 5, 13, 48, 49).2 In order to make this practice at least partially self-contained, a moderate amount of discussion is provided in areas relating to ASTM and other documents. Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, and exposure units.
1.3 This practice is restricted to direct applications related to surveillance programs that are established in support of the operation, licensing, and regulation of LWR nuclear power plants. Procedures and data related to the analysis, interpretation, and application of test reactor results are addressed in Practice E1006, Guide E900, and Practice E1035.
1.4 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.
1.5 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.
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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.
Designation: E853 − 23
Standard Practice for
Analysis and Interpretation of Light-Water Reactor
1
Surveillance Neutron Exposure Results
This standard is issued under the fixed designation E853; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee.
1.1 This practice covers the methodology, summarized in
Annex A1, to be used in the analysis and interpretation of
2. Referenced Documents
neutron exposure data obtained from LWR pressure vessel
4
surveillance programs and, based on the results of that analysis, 2.1 ASTM Standards:
establishes a formalism to be used to evaluate present and E185 Practice for Design of Surveillance Programs for
future condition of the pressure vessel and its support struc- Light-Water Moderated Nuclear Power Reactor Vessels
2 3
tures (1-74). E482 Guide for Application of Neutron Transport Methods
for Reactor Vessel Surveillance
1.2 This practice relies on, and ties together, the application
E509 Guide for In-Service Annealing of Light-Water Mod-
of several supporting ASTM standard practices, guides, and
2 erated Nuclear Reactor Vessels
methods (see Master Matrix E706) (1, 5, 13, 48, 49). In order
E706 Master Matrix for Light-Water Reactor Pressure Vessel
to make this practice at least partially self-contained, a mod-
Surveillance Standards
erate amount of discussion is provided in areas relating to
E844 Guide for Sensor Set Design and Irradiation for
ASTM and other documents. Support subject areas that are
Reactor Surveillance
discussed include reactor physics calculations, dosimeter se-
E854 Test Method for Application and Analysis of Solid
lection and analysis, and exposure units.
State Track Recorder (SSTR) Monitors for Reactor Sur-
1.3 This practice is restricted to direct applications related to
veillance
surveillance programs that are established in support of the
E900 Guide for Predicting Radiation-Induced Transition
operation, licensing, and regulation of LWR nuclear power
Temperature Shift in Reactor Vessel Materials
plants. Procedures and data related to the analysis,
E910 Test Method for Application and Analysis of Helium
interpretation, and application of test reactor results are ad-
Accumulation Fluence Monitors for Reactor Vessel Sur-
dressed in Practice E1006, Guide E900, and Practice E1035.
veillance
1.4 This standard does not purport to address all of the
E944 Guide for Application of Neutron Spectrum Adjust-
safety concerns, if any, associated with its use. It is the ment Methods in Reactor Surveillance
responsibility of the user of this standard to establish appro-
E1005 Test Method for Application and Analysis of Radio-
priate safety, health, and environmental practices and deter- metric Monitors for Reactor Vessel Surveillance
mine the applicability of regulatory limitations prior to use.
E1006 Practice for Analysis and Interpretation of Physics
1.5 This international standard was developed in accor- Dosimetry Results from Test Reactor Experiments
dance with internationally recognized principles on standard-
E1018 Guide for Application of ASTM Evaluated Cross
ization established in the Decision on Principles for the Section Data File
Development of International Standards, Guides and Recom-
E1035 Practice for Determining Neutron Exposures for
Nuclear Reactor Vessel Support Structures
E1214 Guide for Use of Melt Wire Temperature Monitors
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
for Reactor Vessel Surveillance
Technology and Applications and is the direct responsibility of Subcommittee
E2006 Guide for Benchmark Testing of Light Water Reactor
E10.05 on Nuclear Radiation Metrology.
Calculations
Current edition approved Sept. 1, 2023. Published September 2023. Originally
approved in 1981. Last previous edition approved in 2018 as E853 – 18. DOI:
10.1520/E0853-23.
2
ASTM Practice E185 gives reference to other standards and references that
4
address the variables and uncertainties associated with property change measure- For referenced ASTM standards, visit the ASTM website, www.astm.org, or
ments. The referenced standards are A370, E8, E21, E23, and E208. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
3
The boldface numbers in parentheses refer to the list of references appended to Standards volume information, refer to the standard’s Document Summ
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: E853 − 18 E853 − 23
Standard Practice for
Analysis and Interpretation of Light-Water Reactor
1
Surveillance Neutron Exposure Results
This standard is issued under the fixed designation E853; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This practice covers the methodology, summarized in Annex A1, to be used in the analysis and interpretation of neutron
exposure data obtained from LWR pressure vessel surveillance programs;programs and, based on the results of that analysis,
2 3
establishes a formalism to be used to evaluate present and future condition of the pressure vessel and its support structures (1-74).
1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods
2
(see Master Matrix E706) (1, 5, 13, 48, 49). In order to make this practice at least partially self-contained, a moderate amount
of discussion is provided in areas relating to ASTM and other documents. Support subject areas that are discussed include reactor
physics calculations, dosimeter selection and analysis, and exposure units.
1.3 This practice is restricted to direct applications related to surveillance programs that are established in support of the operation,
licensing, and regulation of LWR nuclear power plants. Procedures and data related to the analysis, interpretation, and application
of test reactor results are addressed in Practice E1006, Guide E900, and Practice E1035.
1.4 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.
1.5 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.
2. Referenced Documents
4
2.1 ASTM Standards:
E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
E509 Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
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, 2018Sept. 1, 2023. Published December 2018September 2023. Originally approved in 1981. Last previous edition approved in 20132018
as E853 – 13.E853 – 18. DOI: 10.1520/E0853-18.10.1520/E0853-23.
2
ASTM Practice E185 gives reference to other standards and references that address the variables and uncertainties associated with property change measurements. The
referencereferenced standards are A370, E8, E21, E23, and E208.
3
The boldface numbers in parentheses refer to the list of references appended to this practice. For an updated set of references, see the E706 Master Matrix.Master Matrix
E706.
4
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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E853 − 23
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance
E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1005 Test Method for Application and Anal
...
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