ASTM E853-13
(Practice)Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results
Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance 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 materials test specimens were exposed. The resultant information will then become part of a data base 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).2
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 ...
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 and health practices and determine the applicability of regulatory limitations prior to use.
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Designation: E853 − 13
Standard Practice for
Analysis and Interpretation of Light-Water Reactor
1
Surveillance 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 2. Referenced Documents
4
1.1 This practice covers the methodology, summarized in 2.1 ASTM Standards:
Annex A1, to be used in the analysis and interpretation of E185 Practice for Design of Surveillance Programs for
neutron exposure data obtained from LWR pressure vessel Light-Water Moderated Nuclear Power Reactor Vessels
surveillance programs; and, based on the results of that E482 Guide for Application of Neutron Transport Methods
analysis, establishes a formalism to be used to evaluate present for Reactor Vessel Surveillance, E706 (IID)
and future condition of the pressure vessel and its support E509 Guide for In-Service Annealing of Light-Water Mod-
2 3
structures (1-74). erated Nuclear Reactor Vessels
E706 MasterMatrixforLight-WaterReactorPressureVessel
1.2 This practice relies on, and ties together, the application
5
Surveillance Standards, E 706(0) (Withdrawn 2011)
of several supporting ASTM standard practices, guides, and
2
E844 Guide for Sensor Set Design and Irradiation for
methods (see Master Matrix E706) (1, 5, 13, 48, 49). In order
Reactor Surveillance, E 706 (IIC)
to make this practice at least partially self-contained, a mod-
E854 Test Method for Application and Analysis of Solid
erate amount of discussion is provided in areas relating to
State Track Recorder (SSTR) Monitors for Reactor
ASTM and other documents. Support subject areas that are
Surveillance, E706(IIIB)
discussed include reactor physics calculations, dosimeter se-
E900 Guide for Predicting Radiation-Induced Transition
lection and analysis, and exposure units.
Temperature Shift in Reactor Vessel Materials, E706 (IIF)
1.3 Thispracticeisrestrictedtodirectapplicationsrelatedto
E910 Test Method for Application and Analysis of Helium
surveillance programs that are established in support of the
Accumulation Fluence Monitors for Reactor Vessel
operation, licensing, and regulation of LWR nuclear power
Surveillance, E706 (IIIC)
plants. Procedures and data related to the analysis,
E944 Guide for Application of Neutron Spectrum Adjust-
interpretation, and application of test reactor results are ad-
ment Methods in Reactor Surveillance, E 706 (IIA)
dressed in Practice E1006, Guide E900, and Practice E1035.
E1005 Test Method for Application and Analysis of Radio-
1.4 This standard does not purport to address all of the
metric Monitors for Reactor Vessel Surveillance, E 706
safety concerns, if any, associated with its use. It is the (IIIA)
responsibility of the user of this standard to establish appro-
E1006 Practice for Analysis and Interpretation of Physics
priate safety and health practices and determine the applica- Dosimetry Results for Test Reactors, E 706(II)
bility of regulatory limitations prior to use.
E1018 Guide for Application of ASTM Evaluated Cross
Section Data File, Matrix E706 (IIB)
1 E1035 Practice for Determining Neutron Exposures for
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Nuclear Reactor Vessel Support Structures
Technology and Applications and is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
Current edition approved June 1, 2013. Published July 2013 Originally approved
in 1981. Last previous edition approved in 2008 as E853 – 01(2008). DOI:
4
10.1520/E0853-13. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
2
ASTM Practice E185 gives reference to other standards and references that contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
address the variables and uncertainties associated with property change measure- Standards volume information, refer to the standard’s Document Summary page on
ments. The reference standards are A370, E8, E21, E23, and E208. the ASTM website.
3 5
The boldface numbers in parentheses refer to the list of references appended to The last approved version of this historical standard is referenced on
this practice. For an updated set of references, see the E706 Master Matrix. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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E853 − 13
E1214 Guide for Use of Melt Wire Temperature Monitors determine the condition of any support structure steels that
for Reactor Vessel Surveillance, E 706 (IIIE) might be subject to
...
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 − 01 (Reapproved 2008) E853 − 13
Standard Practice for
Analysis and Interpretation of Light-Water Reactor
1
Surveillance Results, E706(IA)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; and, based on the results of that analysis, establishes a
2 3
formalism to be used to evaluate present and future condition of the pressure vessel and its support structures (1-7074).
1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and
2
methods (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.
NOTE 1—(Figure 1 is deleted in the latest update. The user is refered to Master Matrix E706 for the latest figure of the standards interconnectivity).
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 E560, 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 and health practices and determine the applicability of regulatory
limitations prior to use.
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, E706 (IID)
E560E509 Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E 706(IC)Guide for In-Service Annealing
of Light-Water Moderated Nuclear Reactor Vessels (Withdrawn 2009)
5
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E 706(0) (Withdrawn 2011)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance,
E706(IIIB)
E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance,
E706 (IIIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706 (IIIA)
E1006 Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
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 Nov. 1, 2008June 1, 2013. Published November 2008July 2013 Originally approved in 1981. Last previous edition approved in 2001 2008 as
E853 – 01.E853 – 01(2008). DOI: 10.1520/E0853-01R08.10.1520/E0853-13.
2
ASTM Practice E185 gives reference to other standards and references that address the variables and uncertainties associated with property change measurements. The
reference 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.
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,Standards Vol 12.02.volume information, refer to the standard’s Document
...
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