ASTM E185-98

Designation: E 185 – 98
Standard Practice for
Conducting Surveillance Tests for Light-Water Cooled
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Nuclear Power Reactor Vessels, E 706 (IF)
This standard is issued under the fixed designation E 185; 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.
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1. Scope lance Dosimetry Results, E 706 (IC)
E 636 Practice for Conducting Supplemental Surveillance
1.1 This practice covers procedures for monitoring the
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Tests for Nuclear Power Reactor Vessels, E 706 (IH)
radiation-induced changes in the mechanical properties of
E 706 Master Matrix for Light-Water Reactor Pressure
ferritic materials in the beltline of light-water cooled nuclear
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Vessel Surveillance Standards, E 706 (O)
power reactor vessels. This practice includes guidelines for
E 844 Guide for Sensor Set Design and Irradiation for
designing a minimum surveillance program, selecting materi-
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Reactor Surveillance, E 706 (IIC)
als, and evaluating test results.
E 853 Practice for Analysis and Interpretation of Light-
1.2 This practice was developed for all light-water cooled
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Water Reactor Surveillance Results, E 706 (IA)
nuclear power reactor vessels for which the predicted maxi-
E 900 Guide for Predicting Neutron Radiation Damage to
mum neutron fluence (E > 1 MeV) at the end of the design
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17 2 21 2
Reactor Vessel Materials, E 706 (IIF)
lifetime exceeds 1 3 10 n/cm (1 3 10 n/m ) at the inside
E 1214 Guide for Use of Melt Wire Temperature Monitors
surface of the reactor vessel.
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for Reactor Vessel Surveillance, E 706 (IIIE)
1.3 This practice does not provide procedures for monitor-
E 1820 Standard Method for Measurement of Fracture
ing the radiation induced changes in properties beyond the
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Toughness
design life, but the procedure described may provide guidance
E 1921 Test Method for the Determination of Reference
for developing such a surveillance program.
Temperature, T , for Ferritic Steels in the Transition
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2. Referenced Documents Range
2.2 Other Document:
2.1 ASTM Standards:
American Society of Mechanical Engineers, Boiler and
A 370 Test Methods and Definitions for Mechanical Testing
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2
Pressure Vessel Code, Sections III and XI
of Steel Products
A 751 Test Methods, Practices and Terminology for Chemi-
3. Terminology
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cal Analysis of Steel Products
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3.1 Definitions:
E 8 Test Methods for Tension Testing of Metallic Materials
3.1.1 adjusted reference temperature (ART)—the reference
E 21 Test Methods for Elevated Temperature Tension Tests
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temperature adjusted for irradiation effects by adding to the
of Metallic Materials
initial RT , the transition temperature shift, and an appro-
NDT
E 23 Test Methods for Notched Bar Impact Testing of
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priate margin.
Metallic Materials
3.1.2 base metal (parent material)—as-fabricated plate ma-
E 208 Test Method for Conducting Drop-Weight Test to
terial or forging material other than a weldment or its corre-
Determine Nil-Ductility Transition Temperature of Ferritic
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sponding heat-affected zone (HAZ).
Steels
3.1.3 beltline—the irradiated region of the reactor vessel
E 482 Guide for Application of Neutron Transport Methods
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(shell material including weld seams and plates or forgings)
for Reactor Vessel Surveillance, E 706 (IID)
that directly surrounds the effective height of the active core,
E 509 Guide for In-Service Annealing of Light-Water
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and adjacent regions that are predicted to experience sufficient
Cooled Nuclear Reactor Vessels
neutron damage to warrant consideration in the selection of
E 560 Practice for Extrapolating Reactor Vessel Surveil-
surveillance material.
3.1.4 Charpy transition temperature curve—a graphic pre-
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sentation of Charpy data, including absorbed energy, lateral
This practice is under the jurisdiction of ASTM Committee E-10 on Nuclear
Technology and Applications and is the direct responsibility of Subcommittee
expansion, and fracture appearance as functions of test tem-
E10.02 on Behavior and Use of Structural Materials.
perature, extending over a range including the lower shelf
Current edition approved Jan. 10, 1998. Published May 1998. Originally
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published as E 185 – 61 T. Last previous edition E 185 – 82 .
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Annual Book of ASTM Standards, Vol 01.03.
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Annual Book of ASTM Standards, Vol 03.01. Available from the American Society of Automotive Engineers, 345 E. 47th St.,
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Annual Book of ASTM Standards, Vol 12.02. New York, NY 10017.
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
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E 185
energy (5 % or less), transition region, and the upper-shelf 3.2.1 The following definitions are intended for application
energy (95 % or greater). to this standard and may not be in agreement with definitions
of the same parameters given in
...