ASTM E2215-02

Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels

SIGNIFICANCE AND USE
4.1 Neutron radiation effects are considered in the design of light-water moderated nuclear power reactors. Changes in system operating parameters may be made throughout the service life of the reactor to account for these effects. A surveillance program is used to measure changes in the properties of actual vessel materials due to the irradiation environment. This practice describes the criteria that should be considered in evaluating surveillance program test capsules.
4.2 Prior to the first issue date of this standard, the design of surveillance programs and the testing of surveillance capsules were both covered in a single standard, Practice E 185. Between its provisional adoption in 1961 and its replacement linked to this standard, Practice E 185 was revised many times (1966, 1970, 1973, 1979, 1982, 1993 and 1998). Therefore, capsules from surveillance programs that were designed and implemented under early versions of the standard were often tested after substantial changes to the standard had been adopted. For clarity, the standard practice for surveillance programs has been divided into the new Practice E 185 that covers the design of new surveillance programs and this standard practice that covers the testing and evaluation of surveillance capsules. A future standard is planned which will recommend procedures for modifying and supplementing existing surveillance programs both in terms of design and testing.
4.3 This standard practice is intended to cover testing and evaluation of all light-water moderated reactor pressure vessel surveillance capsules. The practice is applicable to testing of capsules from surveillance programs designed and implemented under all previous versions of Practice E 185.
4.4 The radiation-induced changes in the properties of the vessel are generally monitored by measuring the Charpy transition temperature, the Charpy upper shelf energy and the tensile properties of specimens from the surveillance program capsules. The significa...
SCOPE
1.1 This practice covers the evaluation of test specimens and dosimetry from light water moderated nuclear power reactor pressure vessel surveillance capsules.
1.2 This practice is one of a series of standard practices that outline the surveillance program required for nuclear reactor pressure vessels. The surveillance program monitors the radiation-induced changes in the ferritic steels that comprise the beltline of a light-water moderated nuclear reactor pressure vessel.
1.3 This practice along with its companion surveillance program practice, Practice E 185, is intended for application in monitoring the properties of beltline materials in any light-water moderated nuclear reactor.
1.4 Modifications to the standard test program and supplemental tests will be described in a separate Standard that is under development to accompany this standard practice and Practice E 185.

General Information

• Status: Historical
• Publication Date: 09-Jun-2002
• 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

• Replaced By: ASTM E2215-10 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Mar-2010
• Referred By: ASTM E1253-21 - Standard Guide for Reconstitution of Charpy-Sized Specimens
• Effective Date: 10-Jun-2002
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 10-Jun-2002
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 10-Jun-2002
• Referred By: ASTM E509/E509M-21 - Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
• Effective Date: 10-Jun-2002
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 10-Jun-2002
• Referred By: ASTM E185-21 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 10-Jun-2002
• Referred By: ASTM E636-20 - Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
• Effective Date: 10-Jun-2002
• Referred By: ASTM E1214-11(2023) - Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
• Effective Date: 10-Jun-2002

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.
Designation:E2215–02
Standard Practice for
Evaluation of Surveillance Capsules from Light-Water
Moderated Nuclear Power Reactor Vessels
This standard is issued under the fixed designation E2215; 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 Light-Water Moderated Nuclear Power Reactor Vessels
E208 Test Method for Conducting Drop-Weight Test to
1.1 This practice covers the evaluation of test specimens
Determine Nil-Ductility Transition Temperature of Ferritic
and dosimetry from light water moderated nuclear power
Steels
reactor pressure vessel surveillance capsules.
E482 Guide for Application of Neutron Transport Methods
1.2 This practice is one of a series of standard practices that
for Reactor Vessel Surveillance, E706 (IID)
outline the surveillance program required for nuclear reactor
E509 Guide for In-Service Annealing of Light-Water Mod-
pressure vessels. The surveillance program monitors the
erated Nuclear Reactor Vessels
radiation-induced changes in the ferritic steels that comprise
E560 PracticeforExtrapolatingReactorVesselSurveillance
the beltline of a light-water moderated nuclear reactor pressure
Dosimetry Results, E 706(IC)
vessel.
E636 Guide for Conducting Supplemental Surveillance
1.3 This practice along with its companion surveillance
Tests for Nuclear Power Reactor Vessels, E 706 (IH)
program practice, Practice E185, is intended for application in
E693 PracticeforCharacterizingNeutronExposuresinIron
monitoring the properties of beltline materials in any light-
and LowAlloy Steels inTerms of Displacements PerAtom
water moderated nuclear reactor.
(DPA), E 706(ID)
1.4 Modifications to the standard test program and supple-
E706 Master Matrix for Light-Water Reactor Pressure Ves-
mental tests will be described in a separate Standard that is
sel Surveillance Standards, E 706(0)
under development to accompany this standard practice and
E844 Guide for Sensor Set Design and Irradiation for
Practice E185.
Reactor Surveillance, E 706(IIC)
2. Referenced Documents E853 Practice for Analysis and Interpretation of Light-
Water Reactor Surveillance Results, E706(IA)
2.1 ASTM Standards:
E900 Guide for Predicting Radiation-Induced Transition
A370 Test Methods and Definitions for Mechanical Testing
Temperature Shift in Reactor Vessel Materials, E706 (IIF)
of Steel Products
E1214 Guide for Use of Melt Wire Temperature Monitors
A751 Test Methods, Practices, andTerminology for Chemi-
for Reactor Vessel Surveillance, E 706 (IIIE)
cal Analysis of Steel Products
E1253 Guide for Reconstitution of Irradiated Charpy-Sized
E8 Test Methods for Tension Testing of Metallic Materials
Specimens
E21 Test Methods for Elevated Temperature Tension Tests
E1820 Test Method for Measurement of Fracture Tough-
of Metallic Materials
ness
E23 Test Methods for Notched Bar Impact Testing of
E1921 Test Method for Determination of Reference Tem-
Metallic Materials
perature, T , for Ferritic Steels in the Transition Range
E170 TerminologyRelatingtoRadiationMeasurementsand o
2.2 Other Documents:
Dosimetry
American Society of Mechanical Engineers, Boiler and
E185 Practice for Design of Surveillance Programs for
Pressure Vessel Code, Sections III and XI
ASMEBoilerandPressureVesselCodeCaseN-629, Useof
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Fracture Toughness Test Data to Establish Reference
Technology and Applications and is the direct responsibility of Subcommittee
Temperature for Pressure Retaining Materials, Section XI,
E10.02 on Behavior and Use of Nuclear Structural Materials.
Division 1
Current edition approved June 10, 2002. Published September 2002. DOI:
10.1520/E2215-02.
Prior to the adoption of these standard practices, surveillance capsule testing
requirements were only contained in Practice E185.
3 4
For referenced ASTM standards, visit the ASTM website, www.astm.org, or Withdrawn. The last approved version of this historical standard is referenced
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM on www.astm.org.
Standards volume information, refer to the standard’s Document Summary page on AvailablefromAmericanSocietyofMechanicalEngineers,ThirdParkAvenue,
the ASTM website. New York, NY 10016.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
E2215–02
ASME Boiler and Pressure Vessel Code Case N-631 Use of 3.1.12 heat-affected-zone (HAZ)—plate material or forging
Fracture Toughness Test Data to Establish Reference material extending outward from, but not including, the weld
Temperature for Pressure Retaining Materials Other Than fusion line in which the microstructure of the base metal has
Bolting for Class 1 Vessels, Section III, Division 1 been altered by the heat of the welding process.
3.1.13 index temperature—that temperature corresponding
3. Terminology
to a predetermined level of absorbed energy, lateral expansion,
3.1 Definitions:
or fracture appearance obtained from the best-fit (average)
3.1.1 adjusted reference temperature (ART)—the reference
Charpy transition curve.
temperature adjusted for irradiation effects by adding to the
3.1.14 lead factor—the ratio of the neutron fluence rate
initial RT , the transition temperature shift, (for example,
NDT (E > 1 MeV) at the specimens in a surveillance capsule to the
see Guide E900), and an appropriate margin to account for
neutron fluence rate (E > 1 MeV) at the reactor pressure vessel
uncertainties.
inside surface peak fluence location.
3.1.2 base metal (parent material)—as-fabricated plate ma-
NOTE 1—Changes in the reactor operating parameters and fuel man-
terial or forging material other than a weld or its corresponding
agement may cause the lead factor to change.
heat-affected-zone (HAZ).
3.1.15 nil-ductility transition temperature (T )—the
NDT
3.1.3 beltline—the irradiated region of the reactor vessel
maximum temperature at which a standard drop weight speci-
(shell material including weld seams and plates or forgings)
men breaks when tested in accordance withTest Method E208.
that directly surrounds the effective height of the active core,
3.1.16 reference material—any steel that has been charac-
and adjacent regions that are predicted to sustain sufficient
terized as to the sensitivity of its mechanical and fracture
neutron damage to warrant consideration in the selection of
toughness properties to neutron radiation embrittlement.
surveillance material.
3.1.17 reference temperature (RT )—see subarticle NB-
NDT
3.1.4 Charpy transition region—the region on the Charpy
2300 of the ASME Boiler and Pressure Vessel Code, Section
transition curve in which toughness increases rapidly with
III, “Nuclear Power Plant Components” for the definition of
rising temperature; in terms of fracture appearance, it is
RT for unirradiated material. ASME Code Cases N-629
NDT
characterized by a change from a primarily cleavage (crystal-
and N-631 provide an alternative definition for the reference
line) fracture mode to a primarily shear (fibrous) fracture
temperature (RT )
To
mode.
3.2 Neutron Exposure Terminology:
3.1.5 Charpy transition temperature curve —a graphic pre-
3.2.1 Definitions of terms related to neutron dosimetry and
sentation of Charpy data, including absorbed energy, lateral
exposure are provided in Terminology E170.
expansion, and fracture appearance as functions of test tem-
perature, extending over a range including the lower shelf
4. Significance and Use
energy (5 % or less shear fracture appearance), transition
region, and the upper-shelf energy (95 % or greater shear 4.1 Neutron radiation effects are considered in the design of
fracture appearance). light-water moderated nuclear power reactors. Changes in
3.1.6 Charpy transition temperature shift—the difference in system operating parameters may be made throughout the
the 30 ft-lbf (41 J) index temperatures for the best fit (average) service life of the reactor to account for these effects. A
Charpy curve measured before and after irradiation. surveillance program is used to measure changes in the
3.1.7 Charpy upper shelf energy level—the average energy properties of actual vessel materials due to the irradiation
valueforallCharpyspecimentests(normallythree)whosetest environment. This practice describes the criteria that should be
temperature is above the Charpy upper shelf onset; specimens considered in evaluating surveillance program test capsules.
tested at temperature greater than 150°F (83°C) above the 4.2 Prior to the first issue date of this standard, the design of
Charpy upper-shelf onset need not be included. The range of surveillance programs and the testing of surveillance capsules
werebothcoveredinasinglestandard,PracticeE185.Between
test temperatures for which energy values were averaged must
be reported as well as the individual energy values. For its provisional adoption in 1961 and its replacement linked to
this standard, Practice E185 was revised many times (1966,
specimens tested in sets of three at each test temperature, the
set having the highest average may be regarded as defining the 1970, 1973, 1979, 1982, 1993 and 1998). Therefore, capsules
upper-shelf energy. from surveillance programs that were designed and imple-
3.1.8 Charpy upper shelf onset—the test temperature above mented under early versions of the standard were often tested
which the fracture appearance of all Charpy specimens tested after substantial changes to the standard had been adopted. For
is nominally 100 % shear. Specimens with 95 % or greater clarity, the standard practice for surveillance programs has
shear may be included in this determination. been divided into the new Practice E185 that covers the design
3.1.9 end-of-life (EOL)—the design lifetime in terms of of new surveillance programs and this standard practice that
years corresponding to the operating license period. covers the testing and evaluation of surveillance capsules. A
3.1.10 fracture strength—in a tensile test, the measured future standard is planned which will recommend procedures
force at fracture divided by the initial cross-sectional area of for modifying and supplementing existing surveillance pro-
the test specimen. grams both in terms of design and testing.
3.1.11 fracture stress—in a tensile test, the measured force 4.3 This standard practice is intended to cover testing and
at fracture divided by the cross-sectional area of the test evaluation of all light-water moderated reactor pressure vessel
specimen at the time of fracture. surveillance capsules. The practice is applicable to testing of
E2215–02
capsules from surveillance programs designed and imple- sponding maximum values for the reactor vessel shall be
mented under all previous versions of Practice E185. determined in accordance with Practices E853 and E560.
4.4 The radiation-induced changes in the properties of the 6.3 Neutronfluencerateandfluencevalues(E>1MeV)and
vessel are generally monitored by measuring the Charpy dparateanddpavaluesshallbedeterminedandrecordedusing
transition temperature, the Charpy upper shelf energy and the a calculated spectrum adjusted or validated by dosimetry
tensile properties of specimens from the surveillance program measurements.
capsules. The significance of these radiation-induced changes
7. Measurement of Mechanical Properties
isdescribedinPracticeE185.Theapplicationofthisdataisthe
7.1 Tension Tests:
subject of Guide E900 and other documents listed in Section 2.
7.1.1 Method—Tension testing shall be conducted in accor-
4.5 Alternative methods exist for testing surveillance cap-
dance with Test Methods E8 and E21.
sule materials. Some supplemental and alternative testing
7.1.2 Test Temperature—In general, the test temperatures
methods are available as indicated in Practice E636. Direct
for each material shall include room temperature, service
measurement of the fracture toughness is also feasible using
temperature, and, if a specimen is available, one intermediate
the T Reference Temperature method defined in Test Method
o
temperature to define the strength versus temperature relation-
E1921 or J-integral techniques defined in Test Method E1820.
ship. Specific consideration should be given to the specific
Additionally hardness testing can be used to supplement
temperatures at which unirradiated specimens have been
standard methods as a means of monitoring the radiation
tested.
response of the materials.
7.1.3 Measurements—Determine yield strength, tensile
4.6 The methodology to be used in the analysis and inter-
strength, fracture strength, fracture stress, total and uniform
pretation of neutron dosimetry data and the determination of
elongation and reduction of area.
neutron fluence is defined in Practice E853.
7.2 Charpy Tests:
4.7 Guide E900 describes the bases used to evaluate the
7.2.1 Method—Charpy tests shall be conducted in accor-
radiation-induced changes in Charpy transition temperature for
dance with Test Methods and Definitions A370 and Test
reactor vessel materials and provides a methodology for
Method E23. Instrumented tests are recommended and should
predicting future values.
be performed in accordance with Practice E636. Broken
Charpy specimens may be reconstituted for supplemental
5. Determination of Capsule Condition
testing in accordance with Guide E1253.
5.1 Visual Examination—A complete visual exam of the
7.2.2 Test Temperature—Specimens for each material shall
capsuleconditionshouldbecompleteduponreceiptandduring
be tested at temperatures selected to define the full energy
disassembly at the testing laboratory. External identification
transition curve. Particular emphasis should be placed on
marks on the capsule shall be verified. Signs of damage or
defining the 30 ft-lbf (41 J) index temperatures and the upper
degradation of the capsule exterior shall be recorded.
shelf energy.
5.2 Capsule Content—The specimen loading pattern should
7.2.3 Measurements—For each test specimen, measure the
be compared to the capsule fabrication records and any
impact energy, lateral expansion, and percent shear fracture
deviations shall be noted. Any evidence of corrosion or other
appearance.
damage to the specimens shall also be noted. The condition of
7.3 Hardness Tests (Optional)—Hardness tests may be per-
any thermal monitors shall be noted and recorded.
formed on irradiated Charpy specimens. The measurements
5.3 Irradiation Temperature History—The average capsule
shallbetakeninareasawayfromthefracturezoneort
...