ASTM E185-10
(Practice)Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
SIGNIFICANCE AND USE
Predictions of neutron radiation effects on pressure vessel steels are considered in the design of light-water moderated nuclear power reactors. Changes in system operating parameters often are made throughout the service life of the reactor vessel to account for radiation effects. Due to the variability in the behavior of reactor vessel steels, a surveillance program is warranted to monitor changes in the properties of actual vessel materials caused by long-term exposure to the neutron radiation and temperature environment of the reactor vessel. This practice describes the criteria that should be considered in planning and implementing surveillance test programs and points out precautions that should be taken to ensure that: (1) capsule exposures can be related to beltline exposures, (2) materials selected for the surveillance program are samples of those materials most likely to limit the operation of the reactor vessel, and (3) the test specimen types are appropriate for the evaluation of radiation effects on the reactor vessel.
The methodology to be used in estimation of neutron exposure obtained for reactor vessel surveillance programs is defined in Guide E482.
The design of a surveillance program for a given reactor vessel must consider the existing body of data on similar materials in addition to the specific materials used for that reactor vessel. The amount of such data and the similarity of exposure conditions and material characteristics will determine their applicability for predicting radiation effects.
SCOPE
1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials.
1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) at the end of license (EOL) exceeds 1 × 1021 neutrons/m2 (1 × 1017 n/cm2) at the inside surface of the reactor vessel.
1.3 This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels.
1.4 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the design life, but the procedure described may provide guidance for developing such a surveillance program.
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
Note 1—The increased complexity of the requirements for a light-water moderated nuclear power reactor vessel surveillance program has necessitated the separation of the requirements into three related standards. Practice E185 describes the minimum requirements for a surveillance program. Practice E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a surveillance program as defined in the current or previous editions of Practice E185. Guide E636 provides guidance for conducting additional mechanical tests. A summary of the many major revisions to Practice E185 since its original issuance is contained in Appendix X1.
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Designation: E185 − 10
StandardPractice for
Design of Surveillance Programs for Light-Water Moderated
1
Nuclear Power Reactor Vessels
This standard is issued under the fixed designation E185; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber 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
2
1.1 This practice covers procedures for designing a surveil- 2.1 ASTM Standards:
lanceprogramformonitoringtheradiation-inducedchangesin
A370Test Methods and Definitions for Mechanical Testing
the mechanical properties of ferritic materials in light-water of Steel Products
moderated nuclear power reactor vessels. This practice in- A751Test Methods, Practices, and Terminology for Chemi-
cludes the minimum requirements for the design of a surveil-
cal Analysis of Steel Products
lance program, selection of vessel material to be included, and
E8/E8MTest Methods for Tension Testing of Metallic Ma-
the initial schedule for evaluation of materials. terials
E21TestMethodsforElevatedTemperatureTensionTestsof
1.2 This practice was developed for all light-water moder-
Metallic Materials
ated nuclear power reactor vessels for which the predicted
E23Test Methods for Notched Bar Impact Testing of Me-
maximum fast neutron fluence (E > 1 MeV) at the end of
tallic Materials
21 2 17 2
license (EOL) exceeds 1×10 neutrons/m (1×10 n/cm )
E170Terminology Relating to Radiation Measurements and
at the inside surface of the reactor vessel.
Dosimetry
1.3 This practice applies only to the planning and design of E208Test Method for Conducting Drop-Weight Test to
surveillance programs for reactor vessels designed and built
Determine Nil-Ductility Transition Temperature of Fer-
after the effective date of this practice. Previous versions of
ritic Steels
Practice E185 apply to earlier reactor vessels. E482Guide for Application of Neutron Transport Methods
for Reactor Vessel Surveillance, E706 (IID)
1.4 This practice does not provide specific procedures for
E636 Guide for Conducting Supplemental Surveillance
monitoring the radiation induced changes in properties beyond
Tests for Nuclear Power Reactor Vessels, E 706 (IH)
the design life, but the procedure described may provide
E844Guide for Sensor Set Design and Irradiation for
guidance for developing such a surveillance program.
Reactor Surveillance, E 706 (IIC)
1.5 The values stated in SI units are to be regarded as the E900Guide for Predicting Radiation-Induced Transition
standard. The values given in parentheses are for information Temperature Shift in ReactorVessel Materials, E706 (IIF)
only.
E1214Guide for Use of Melt Wire Temperature Monitors
for Reactor Vessel Surveillance, E 706 (IIIE)
NOTE 1—The increased complexity of the requirements for a light-
water moderated nuclear power reactor vessel surveillance program has
E1253Guide for Reconstitution of Irradiated Charpy-Sized
necessitated the separation of the requirements into three related stan-
Specimens
dards. Practice E185 describes the minimum requirements for a surveil-
E1820Test Method for Measurement of FractureToughness
lance program. Practice E2215 describes the procedures for testing and
E1921 Test Method for Determination of Reference
evaluation of surveillance capsules removed from a surveillance program
as defined in the current or previous editions of Practice E185. Guide Temperature, T , for Ferritic Steels in the Transition
o
E636 provides guidance for conducting additional mechanical tests. A
Range
summary of the many major revisions to Practice E185 since its original
E2215Practice for Evaluation of Surveillance Capsules
issuance is contained in Appendix X1.
from Light-Water Moderated Nuclear Power ReactorVes-
sels
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
2
E10.02 on Behavior and Use of Nuclear Structural Materials. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved March 1, 2010. Published April 2010. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1961 as E185–61T. Last previous edition approved in 2002 as Standards volume information, refer to the standard’s Document Summary page on
E185–02. DOI: 10.1520/E0185-10. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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E185 − 10
3
2.2 ASME Standards: 3.1.10 lead factor—the ratio of the peak neutron fluence
American Society of Mechanical Engineers, Boile
...
This document is not anASTM standard and is intended only to provide the user of anASTM 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:E 185–94 Designation: E185 – 10
Standard Practice for
Conducting Surveillance Tests for Light-Water Cooled
Nuclear Power Reactor Vessels, E 706 (IF)Design of
Surveillance Programs for Light-Water Moderated Nuclear
1
Power Reactor Vessels
This standard is issued under the fixed designation E185; 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 (ϵ) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1This practice covers procedures for monitoring the radiation-induced changes in the mechanical properties of ferritic
materials in the beltline of light-water cooled nuclear power reactor vessels. This practice includes guidelines for designing a
minimum surveillance program, selecting materials, and evaluating test results.
1.2This practice was developed for all light-water cooled nuclear power reactor vessels for which the predicted maximum
neutron fluence (
1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the
mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. This practice includes the
minimumrequirementsforthedesignofasurveillanceprogram,selectionofvesselmaterialtobeincluded,andtheinitialschedule
for evaluation of materials.
1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum
21
> 1 MeV) at the end of license (EOL) exceeds 13 10
fast neutron fluence (E > 1 MeV) at the end of the design lifetime exceeds 1310
2
17 2 21 2
neutrons/m (13 10 n/cm (1310 n/m ) at the inside surface of the reactor vessel.
1.3This practice does not provide procedures for monitoring the radiation induced changes in properties beyond the design life,
but the procedure described may provide guidance for developing such a surveillance program.
1.3 This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after
the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels.
1.4 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the
design life, but the procedure described may provide guidance for developing such a surveillance program.
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
NOTE 1—The increased complexity of the requirements for a light-water moderated nuclear power reactor vessel surveillance program has necessitated
the separation of the requirements into three related standards. Practice E185 describes the minimum requirements for a surveillance program. Practice
E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a surveillance program as defined in the current or
previous editions of Practice E185. Guide E636 provides guidance for conducting additional mechanical tests. A summary of the many major revisions
to Practice E185 since its original issuance is contained in Appendix X1.
2. Referenced Documents
2
2.1 ASTM Standards:
A370 Test Methods and Definitions for Mechanical Testing of Steel Products
A751 Test Methods, Practices, and Terminology for Chemical Analysis of Steel Products
E88/E8M Test Methods for Tension Testing of Metallic Materials
E21 Test Methods for Elevated Temperature Tension Tests of Metallic Materials
E23 Test Methods for Notched Bar Impact Testing of Metallic Materials
E208170 Terminology Relating to Radiation Measurements and Dosimetry
1
This practice is under the jurisdiction ofASTM Committee E-10 E10 on Nuclear Technology andApplications and is the direct responsibility of Subcommittee E10.02
on Behavior and Use of Structural Materials.
ϵ2
Current edition approved March 15, 1994. Published June 1994. Originally published as E 185–61T. Last previous edition E 185–82 . on Behavior and Use of Nuclear
Structural Materials.
Current edition approved March 1, 2010. PublishedApril 2010. Originally approved in 1961 as E185 – 61 T. Last previous edition approved in 2002 as E185 – 02. DOI:
10.1520/E0185-10.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
, Vol 01.03.volume information, ref
...
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