ASTM E531-76(1996)e1
(Practice)Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials
Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials
SCOPE
1.1 This practice covers procedures for specimen testing to establish changes occurring in the mechanical properties due to irradiation and thermal effects of nuclear component metallic materials where these materials are used for high temperature applications above 370°C (700°F).
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e1
Designation: E 531 – 76 (Reapproved 1996)
Standard Practice for
Surveillance Testing of High-Temperature Nuclear
Component Materials
This standard is issued under the fixed designation E 531; 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 (e) indicates an editorial change since the last revision or reapproval.
e NOTE—Keywords were added editorially in August 1996.
1. Scope ence, and Spectra by Radioactivation Techniques
E 399 Test Method for Plane-Strain Fracture Toughness of
1.1 This practice covers procedures for specimen testing to
Metallic Materials
establish changes occurring in the mechanical properties due to
E 453 Practice for Examination of Fuel Element Cladding
irradiation and thermal effects of nuclear component metallic
Including the Determination of the Mechanical Properties
materials where these materials are used for high temperature
E 482 Guide for Application of Neutron Transport Methods
applications above 370°C (700°F).
for Reactor Vessel Surveillance, E706 (IID)
2. Referenced Documents E 844 Guide for Sensor Set Design and Irradiation for
Reactor Surveillance, E706 (IIC)
2.1 ASTM Standards:
A 370 Test Methods and Definitions for Mechanical Testing
3. Significance and Use
of Steel Products
3.1 The requirements contained herein can be used as a
E 3 Methods of Preparation of Metallographic Specimens
basis for establishing conditions for safe operation of critical
E 8 Test Methods for Tension Testing of Metallic Materials
components. The requirements provide for general plant as-
E 21 Test Methods for Elevated Temperature Tension Tests
sessment and verification that materials meet design criteria.
of Metallic Materials
The test specimens and procedures presented in this practice
E 23 Test Methods for Notched Bar Impact Testing of
are for guidance when establishing a surveillance program.
Metallic Materials
3.2 This practice for high-temperature materials surveil-
E 29 Practice for Using Significant Digits in Test Data to
lance programs is used when nuclear reactor component
Determine Conformance with Specifications
materials are monitored by specimen testing. Periodic testing is
E 45 Test Methods for Determining the Inclusion Content
performed through the service life of the components to assess
of Steel
changes in selected material properties that are caused by
E 112 Test Methods for Determining the Average Grain
neutron irradiation and thermal effects. The properties are those
Size
used as design criteria for the respective nuclear components.
E 139 Practice for Conducting Creep, Creep-Rupture, and
The extent of material property change caused by neutron
Stress-Rupture Tests of Metallic Materials
irradiation depends on the composition and structure of the
E 184 Practice for Effects of High-Energy Neutron Radia-
initial material, its conditioning in component fabrication, as
tion on the Mechanical Properties of Metallic Materials,
5 well as the nature of the irradiation exposure. The need for
E706 (IB)
surveillance arises from a concern of specific material behavior
E 185 Practice for Conducting Surveillance Tests for Light
5 under all irradiation conditions including spectrum and rate
Water-Cooled Nuclear Power Reactor Vessels, E706 (IF)
effects on material properties.
E 206 Definitions of Terms Relating to Fatigue Testing and
the Statistical Analysis of Fatigue Data
4. Description of Term
E 261 Practice for Determining Neutron Fluence Rate, Flu-
4.1 test specimen—a coupon or a piece of metal cut from a
larger metal piece which is then formed to final size for testing
This recommended practice is under the jurisdiction of ASTM Committee E-10
to determine physical or mechanical properties.
on Nuclear Technology and Applicationsand is the direct responsibility of Subcom-
mittee E10.02 on Behavior and Use of Metallic Materials in Nuclear Systems.
5. Test Specimens
Current edition approved March 26, 1976. Published July 1976. Originally
published as E 531–75. Last previous edition E 531–75.
5.1 Pre-Exposure Material Characterization—It is impor-
Annual Book of ASTM Standards, Vol 01.03.
3 tant that test specimen materials be characterized prior to
Annual Book of ASTM Standards, Vol 03.01.
Annual Book of ASTM Standards, Vol 14.02. exposure and that the following should be considered as a
Annual Book of ASTM Standards, Vol 12.02.
minimum:
Discontinued—see 1986 Annual Book of ASTM Standards, Vol 03.01.
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
E 531
5.1.1 Process history, material designation, manufacturer, control specimens shall be identical with the surveillance
heat number, weld and fabrication procedures used, and heat specimens.
treatment,
5.3.3 Surface Condition—Test specimens where surface
5.1.2 Original location and orientation in the parent mate-
condition is critical to the test results should not be finish
rial,
machined in such critical areas (Charpy notch, fatigue speci-
5.1.3 Specimen weight and dimensions,
men test area, surface of density change sample) until just prior
5.1.4 Metallographic characteristics (grain size, microstruc- to test. Specimens should be oversized to allow for removal of
ture, and inclusion content established in accordance with Test
at least 0.1 mm of surface prior to test. Where possible, test
Methods E 45 and E 112), specimens with the exception of weight change specimens
5.1.5 Chemical analysis results, shall be encapsulated in an inert environment so as to deter-
mine only the effect of neutron irradiation and temperature on
5.1.6 All specimens shall be taken from the specified
location and orientation specified in Test Methods and Defini- mechanical or physical properties. It is recognized the integrity
of the encapsulation may be breached in some cases during
tions A 370 and Test Methods E 8, and
long exposure and an allowance for final machining even of the
5.1.7 Mechanical properties including yield strength, tensile
encapsulated specimens should be considered. This will ensure
strength, stress rupture life, creep strength, fatigue strength,
a meaningful comparison between baseline and exposed speci-
and impact strength as a function of test temperature.
mens.
5.1.8 The information described in 5.1.1-5.1.7 should be
reported in a single document. 5.3.4 Number of Specimens—The number of specimens
5.2 Post Exposure Material Characterization—After expo- employed for mechanical property testing should be selected so
sure, the following should be reported: as to include each critical component that varies significantly in
5.2.1 Observations from visual examination, composition, processing, or in exposure conditions from simi-
lar components. Specific recommendations as to number of
5.2.2 Changes in specimen weight and dimensions,
specimens will be found in the respective specimen sections.
5.2.3 Metallographic characteristics (grain size, microstruc-
At least four sets of specimens shall be included in each
ture, and inclusion content),
surveillance program.
5.2.4 Results of chemical analysis,
5.3.5 Material—Test specimens shall be taken from the
5.2.5 Appropriate mechanical properties being surveyed
material used in component fabrication. The material shall be
including considerations of changes in tensile strength, stress-
processed at the same time as the component or processed in a
to-rupture strength, creep strength, fatigue strength, impact
fashion identical to the component surveyed. Weld and heat-
strength (control tests are recommended to be performed
affected zone test specimens shall be taken from equivalent
simultaneously with the tests of exposed specimens to ensure
material welded at the same time as the particular component
that deviations in test results can be attributed to the exposed
or equivalent material welded with the same welding param-
specimen’s environment and not to variations in testing meth-
eters. It is not necessary to include each heat or minor
ods), and
variation, but only to select those receiving the highest expo-
5.2.6 Optional quantitative examination of surface chemis-
sure or those previously found to be most sensitive to neutron
try and subsequent changes.
irradiation and temperature or those that can restrict the
5.2.7 Exposed test specimens should be cleaned in accor-
operation of the reactor. Test specimens may be taken from
dance with accepted cleaning procedures. (Refer to Subcom-
components periodically removed from the reactor for other
mittee G01.08 for practices for preparing, cleaning, and evalu-
reasons. These specimens can be used to provide supplemental
ating test specimens.)
surveillance information. For this information to be meaningful
5.3 Specimen Preparation—Test specimens shall be stan-
a full characterization of the pre-exposure condition must be
dard recommended specimens where possible as described in
available along with measured exposure conditions.
Test Methods E 8, E 21 and E 23 and Practice E 139. The use
5.4 Tension Test Specimens—The type and size of specimen
of the word specimen or words test specimen as used in this
practice is described in Section 4. to be used shall conform to the smaller sizes as recommended
in Test Methods E 8 and E 21. Either threaded or button-head
5.3.1 The test area of a specimen (for example, Charpy
ends will be acceptable. For plate or sheet specimens, pin ends
notch, reduced section of a fatigue specimen) may be left
as described in Test Methods E 8 are recommended. The
unfinished if further environmental exposure prior to testing is
location and orientation of test specimens shall be as defined in
anticipated.
Test Methods E 8 or Test Methods and Definitions A 370, or in
5.3.2 Size—In general, due to the limited space available in
Practice E 185. Both base metal and weld metal specimens will
surveillance capsules the smaller sizes of test specimens are
be taken. A set of tension specimens shall consist of three each
recommended. Where it is not possible to use specimens of the
base metal and weld metal.
recommended size, the least deviation possible from recom-
mended sizes should be adhered to. Non-standard specimens 5.5 Creep and Stress-Rupture in Specimens—The type and
shall be evaluated prior to use as surveillance specimens to size of specimen to be used shall be the same as those used for
ensure that test results from the use of non-standard specimens tension specimens except that button-head or pinned-end
can be correlated with test results from specimens of recom- specimens are recommended for high-temperature testing.
mended size. In the event that non-standard specimens are used Practice E 453 describes the attention that must be paid to
for surveillance specimens, the archive, base line, and thermal specimen alignment and dimensional tolerances. One set of
E 531
tests shall be conducted at the operating temperature of the accordance with Methods E 3. Test specimens that are suscep-
component of interest. A set shall comprise a minimum of six tible to corrosion in room-temperature air shall be stored as
stress rupture tests at six different stress levels. The stress soon as practicable after preparation in an inert dry gas or
levels should be selected so that the time-to-rupture ranges vacuum. A set of specimens shall consist of ten each of base
from not less than 100 h to at least 3000 h. Creep strain metal and weld metal.
measurements may be made if desired. 5.7 Swelling Specimens—The swelling specimens shall be
5.6 Low-Cycle Fatigue Specimens—For base metal the type right circular cylinders 5.0 mm diameter and 10.0 mm long.
and size of specimen to be used may be the “hourglass” type The sharp-cornered specimens shall be finished by turning or
with threaded or button-head ends as shown in Fig. 1. For weld grinding and have a surface finish of 0.2 μm R (8 μin. AA).
a
metal specimens the uniform gage type may be used. Machin- The specimens shall be degreased in suitable solvent and stored
ing and polishing of the test specimens shall be performed with in an inert gas or vacuum.
care so as to minimize the effects of specimen preparation on 5.8 Charpy Impact Specimens—The specimens to be used
fatigue life. In the final stages of machining, material shall be shall conform to the Charpy V-notch specimens recommended
removed in the radial thickness amounts of 0.2 mm until 0.1 in Test Methods E 23. The notch shall not be formed prior to
mm remains. After exposure the final 0.075 mm shall be exposure as a surveillance specimen. The location and orien-
removed by cylindrical grinding at no more than 0.005 mm per tation of test specimens shall be as defined in Practice E 185
pass. The final 0.025 mm shall be buffed and finished with an and Test Methods and Definitions A 370. A set of specimens
0.2 μm R (8 μin. AA) surface roughness. After polishing, all shall be made up of twelve each base metal, heat-affected zone,
a
remaining grinding and polishing marks shall be longitudinal and weld metal.
and any circumferential grinding marks must be removed. The
6. Irradiation Conditions
finished specimens shall be degreased in suitable solvent.
Specimens to be exposed to liquid sodium shall not be 6.1 Introduction—The intent of the section on irradiation
degreased in halogenated solvents. If surface observations are conditions is to provide guidance on how to place surveillance
to be made, the test specimen may be electropolished in samples to obtain the desired irradiation conditions in terms of
NOTE 1—A 5 0.2 μm R (8 min AA).
a
Metric Conversion
mm in.
0.3 0.01
6.35 0.250
8.4 0.33
12.68 0.499
12.70 0.500
19.1 0.75
38.1 1.5
82.6 3.25
FIG. 1 Standard Hour-Glass Low Cycle Fatigue Specimen (Threaded Ends (a) and Button Head (b))
E 531
temperature, neutron flux, and neutron spectrum to ensure a 7. Measurement of Neutron Exposure
realistic evaluation of the component that the surveillance
7.1 The neutron flux and neutron energy spectrum at the
specimen is representing.
surveillance location shall be given as well as the method used
6.2 Irradiation Temperature—It is very important that ad-
for determination. All assumptions should be clearly stated,
equate consideration be given to test specimens to ensure that and all physical constants, such as cross sections, half lives,
they experience the correct temperature during irradiation.
fission yields, etc., should be listed. The neutron flux level
Temperature must be controlled for the surveillance specimens should be determined using more than
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