ASTM E185-15e1

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

SIGNIFICANCE AND USE
4.1 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.  
4.2 The methodology to be used in estimation of neutron exposure obtained for reactor vessel surveillance programs is defined in Guides E482 and E853.  
4.3 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. New advanced light-water small modular reactor designs with a nominal design output of 300 MWe or less have not been specifically considered in this practice. 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) exceeds 1 × 1021 neutrons/m 2  (1 × 1017 n/cm2) at the inside surface of the ferritic steel reactor vessel.  
1.3 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the design life. Practice E2215 addresses changes to the withdrawal schedule during and beyond the design life.  
1.4 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 design of a surveillance program. Practice E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a reactor vessel. 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.
Note 2: 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. See Appendix X1.

General Information

• Status: Historical
• Publication Date: 31-May-2015
• ICS: 27.120.10 - Reactor engineering
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.02 - Behavior and Use of Nuclear Structural Materials

Relations

• Replaces: ASTM E185-15 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2015
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 01-Jun-2015
• Referred By: ASTM E636-20 - Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2015
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jun-2015
• Referred By: ASTM E1214-11(2023) - Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jun-2015
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 01-Jun-2015
• Referred By: ASTM E1297-18 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
• Effective Date: 01-Jun-2015
• Referred By: ASTM E1018-20e1 - Standard Guide for Application of ASTM Evaluated Cross Section Data File
• Effective Date: 01-Jun-2015
• Referred By: ASTM E1253-21 - Standard Guide for Reconstitution of Charpy-Sized Specimens
• Effective Date: 01-Jun-2015
• Referred By: ASTM E1006-21 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• Effective Date: 01-Jun-2015
• Referred By: ASTM E509/E509M-21 - Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
• Effective Date: 01-Jun-2015
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 01-Jun-2015
• Referred By: ASTM E2215-19 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2015

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
´1
Designation: E185 − 15
Standard Practice 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
ε NOTE—Paragraph X1.8 was corrected editorially in October 2015.
earlier reactor vessels. See Appendix X1.
1. Scope
1.1 This practice covers procedures for designing a surveil-
2. Referenced Documents
lanceprogramformonitoringtheradiation-inducedchangesin 2
2.1 ASTM Standards:
the mechanical properties of ferritic materials in light-water
A370Test Methods and Definitions for Mechanical Testing
moderated nuclear power reactor vessels. New advanced light-
of Steel Products
water small modular reactor designs with a nominal design
A751Test Methods, Practices, and Terminology for Chemi-
output of 300 MWe or less have not been specifically consid-
cal Analysis of Steel Products
ered in this practice. This practice includes the minimum
E8/E8MTest Methods for Tension Testing of Metallic Ma-
requirements for the design of a surveillance program, selec-
terials
tion of vessel material to be included, and the initial schedule
E21TestMethodsforElevatedTemperatureTensionTestsof
for evaluation of materials.
Metallic Materials
1.2 This practice was developed for all light-water moder-
E23Test Methods for Notched Bar Impact Testing of Me-
ated nuclear power reactor vessels for which the predicted tallic Materials
21
maximum fast neutron fluence (E > 1 MeV) exceeds 1×10
E170Terminology Relating to Radiation Measurements and
2 17 2
neutrons/m (1×10 n/cm )attheinsidesurfaceoftheferritic Dosimetry
steel reactor vessel.
E208Test Method for Conducting Drop-Weight Test to
Determine Nil-Ductility Transition Temperature of Fer-
1.3 This practice does not provide specific procedures for
ritic Steels
monitoring the radiation induced changes in properties beyond
E482Guide for Application of Neutron Transport Methods
the design life. Practice E2215 addresses changes to the
for Reactor Vessel Surveillance, E706 (IID)
withdrawal schedule during and beyond the design life.
E636 Guide for Conducting Supplemental Surveillance
1.4 The values stated in SI units are to be regarded as the
Tests for Nuclear Power Reactor Vessels, E 706 (IH)
standard. The values given in parentheses are for information
E844Guide for Sensor Set Design and Irradiation for
only.
Reactor Surveillance, E 706 (IIC)
NOTE 1—The increased complexity of the requirements for a light-
E853PracticeforAnalysisandInterpretationofLight-Water
water moderated nuclear power reactor vessel surveillance program has
Reactor Surveillance Results
necessitated the separation of the requirements into three related stan-
dards. Practice E185 describes the minimum requirements for design of a E900Guide for Predicting Radiation-Induced Transition
surveillance program. Practice E2215 describes the procedures for testing
Temperature Shift in Reactor Vessel Materials
and evaluation of surveillance capsules removed from a reactor vessel.
E1214Guide for Use of Melt Wire Temperature Monitors
GuideE636providesguidanceforconductingadditionalmechanicaltests.
for Reactor Vessel Surveillance, E 706 (IIIE)
AsummaryofthemanymajorrevisionstoPracticeE185sinceitsoriginal
E1253Guide for Reconstitution of Irradiated Charpy-Sized
issuance is contained in Appendix X1.
NOTE 2—This practice applies only to the planning and design of Specimens
surveillance programs for reactor vessels designed and built after the
E1820Test Method for Measurement of FractureToughness
effectivedateofthispractice.PreviousversionsofPracticeE185applyto
E1921 Test Method for Determination of Reference
Temperature, T , for Ferritic Steels in the Transition
o
Range
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applications and 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
CurrenteditionapprovedJune1,2015.PublishedJuly2015.Originallyapproved contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
in 1961 as E185–61T. Last previous edition approved in 2010 as E185–10. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/E0185-15E01. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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´1
E185 − 15
E2215Practice for Evaluation o
...

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.
´1
Designation: E185 − 15 E185 − 15
Standard Practice 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. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1
ε NOTE—Paragraph X1.8 was corrected editorially in October 2015.
1. 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. New advanced light-water small
molecularmodular reactor designs with a nominal design output of 300 MWe or less have not been specifically considered in this
practice. 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
21 2 17 2
fast neutron fluence (E > 1 MeV) exceeds 1 × 10 neutrons/m (1 × 10 n/cm ) at the inside surface of the ferritic steel reactor
vessel.
1.3 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the
design life. Practice E2215 addresses changes to the withdrawal schedule during and beyond the design life.
1.4 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 design of a surveillance program.
Practice E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a reactor vessel. 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.
NOTE 2—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. See 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
E8/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
E170 Terminology Relating to Radiation Measurements and Dosimetry
E208 Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
E636 Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results
E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
E1214 Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)
E1253 Guide for Reconstitution of Irradiated Charpy-Sized Specimens
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.02 on
Behavior and Use of Nuclear Structural Materials.
Current edition approved June 1, 2015. Published July 2015. Originally approved in 1961 as E185 – 61 T. Last previous edition approved in 2010 as E185 – 10. DOI:
10.1520/E0185-15.10.1520/E0185-15E01.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM websit
...