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ASTM D5139-12

(Specification)

Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants

Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants

ABSTRACT
This specification defines the size composition and surface preparation requirements for the preparation of test samples used for qualification testing of coatings utilized in nuclear power plant construction and maintenance. All panels should be carbon steel. Materials shall be tested for abrasion, and shall conform to specified requirements of steel samples, and concrete blocks.
SIGNIFICANCE AND USE
4.1 This specification provides uniform requirements for the preparation of test samples used for testing of coatings and linings to be used in nuclear power plants.  
4.2 At the users discretion, this standard may also be used when preparing samples to be tested for the purpose of assessing performance attributes for coating and lining systems that may be applied in other types of power plants or for other industrial facilities.  
4.3 Users of this guide must ensure that coatings work complies not only with this guide, but also with the licensee’s plant-specific quality assurance program and licensing commitments.
SCOPE
1.1 This specification defines the size, composition, surface preparation, and coating application variables for preparing samples for evaluating coatings and linings over various substrates.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

General Information

Status
Historical
Publication Date
30-Jun-2012
ICS
27.120.20 - Nuclear power plants. Safety
Technical Committee
D33 - Protective Coating and Lining Work for Power Generation Facilities
Drafting Committee
D33.02 - Service and Material Parameters
Current Stage
Ref Project

Relations

Replaces
ASTM D5139-10 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants
Effective Date
01-Jul-2012
Replaced By
ASTM D5139-19 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants
Effective Date
01-Jun-2019
Referred By
ASTM D7230-06(2021) - Standard Guide for Evaluating Polymeric Lining Systems for Water Immersion in Coating Service Level III Safety-Related Applications on Metal Substrates
Effective Date
01-Jul-2012
Referred By
ASTM D4082-10(2023) - Standard Test Method for Effects of Gamma Radiation on Coatings for Use in Nuclear Power Plants
Effective Date
01-Jul-2012
Referred By
ASTM D3912-10(2023) - Standard Test Method for Chemical Resistance of Coatings and Linings for Use in Nuclear Power Plants
Effective Date
01-Jul-2012
Referred By
ASTM D6943-15(2019) - Standard Practice for Immersion Testing of Industrial Protective Coatings and Linings
Effective Date
01-Jul-2012
Referred By
ASTM D5144-08(2021) - Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
Effective Date
01-Jul-2012
Referred By
ASTM D8104-17(2023) - Standard Guide for Determining Coating Qualification Test Data Applicability
Effective Date
01-Jul-2012
Referred By
ASTM D3911-16(2021) - Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis Accident (DBA) Conditions
Effective Date
01-Jul-2012
Referred By
ASTM D8157-19 - Standard Guide for Qualification Testing of Coatings Used in Coating Service Level I in Nuclear Power Plants
Effective Date
01-Jul-2012

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ASTM D5139-12 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power PlantsASTM D5139-12 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants
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REDLINE ASTM D5139-12 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power PlantsREDLINE ASTM D5139-12 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants
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Technical specification
REDLINE ASTM D5139-12 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants
English language
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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:D5139 −12
Standard Specification for
Sample Preparation for Qualification Testing of Coatings to
1
be Used in Nuclear Power Plants
This standard is issued under the fixed designation D5139; 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 D4260 Practice for Liquid and Gelled Acid Etching of
Concrete
1.1 This specification defines the size, composition, surface
D4538 Terminology Relating to Protective Coating and
preparation, and coating application variables for preparing
Lining Work for Power Generation Facilities
samples for evaluating coatings and linings over various
D4541 Test Method for Pull-Off Strength of Coatings Using
substrates.
Portable Adhesion Testers
1.2 The values stated in inch-pound units are to be regarded
D7234 Test Method for Pull-OffAdhesion Strength of Coat-
as standard. The values given in parentheses are mathematical
ings on Concrete Using Portable Pull-Off Adhesion Tes-
conversions to SI units that are provided for information only
ters
and are not considered standard.
3
2.2 American Concrete Institute:
1.3 This standard does not purport to address all of the
ACI 308 Guide to Curing Concrete
safety concerns, if any, associated with its use. It is the
ACI Cement and Concrete Terminology
responsibility of the user of this standard to establish appro-
4
2.3 American National Standards Institute (ANSI):
priate safety and health practices and determine the applica-
ANSI N5.12–1974 Protective Coatings (Paints) for the
bility of regulatory limitations prior to use.
Nuclear Industry, paragraph 7.4.3
2. Referenced Documents
3. Terminology
2
2.1 ASTM Standards:
3.1 Definitions—Definitions for use with this standard are
A36/A36M Specification for Carbon Structural Steel
shown in Terminology D4538 or other applicable standards.
C33/C33M Specification for Concrete Aggregates
3.2 Definitions of Terms Specific to This Standard:
C150/C150M Specification for Portland Cement
3.2.1 bughole (surface air void), n—a small regular or
C192/C192M Practice for Making and Curing Concrete Test
irregular cavity, usually not exceeding 1.5 mm in diameter,
Specimens in the Laboratory
resulting from entrapment of air bubbles in the surface of
C260 Specification for Air-Entraining Admixtures for Con-
formed concrete during placement and consolidation (ACI
crete
Cement and Concrete Terminology).
C494/C494M Specification for Chemical Admixtures for
Concrete
3.2.2 curing compound, n—a liquid that can be applied as a
C618 Specification for Coal Fly Ash and Raw or Calcined
coating to the surface of newly placed concrete to retard the
Natural Pozzolan for Use in Concrete
loss of water and, in the case of pigmented compounds, to
D3912 Test Method for Chemical Resistance of Coatings
reflect heat so as to provide an opportunity for the concrete to
and Linings for Use in Nuclear Power Plants
develop its properties in a favorable temperature and moisture
D4258 Practice for Surface Cleaning Concrete for Coating
environment (ACI Cement and Concrete Terminology).
D4259 Practice for Abrading Concrete
4. Significance and Use
4.1 This specification provides uniform requirements for the
1
This specification is under the jurisdiction of ASTM Committee D33 on
preparation of test samples used for testing of coatings and
ProtectiveCoatingandLiningWorkforPowerGenerationFacilitiesandisthedirect
responsibility of Subcommittee D33.02 on Service and Material Parameters.
linings to be used in nuclear power plants.
Current edition approved July 1, 2012. Published August 2012. Originally
approved in 1990. Last previous edition approved in 2010 as D5139 – 10. DOI:
10.1520/D5139-12.
2 3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or Available fromAmerican Concrete Institute (ACI), P.O. Box 9094, Farmington
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Hills, MI 48333-9094, http://www.concrete.org.
4
Standards volume information, refer to the standard’s Document Summary page on Available from American National Standards Institute (ANSI), 25 W. 43rd St.,
the ASTM website. 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
D5139−12
FIG. 1Concrete Test Block Face Designation
4.2 At the users discretion, this standard may also be used
Cement Specification C150/C150M, 22.2 lb (10.07 kg)
Type II low alkali
when preparing samples to be tested for the purpose of
Gravel Specification C33/C33M, 45.3 lb (20.55 kg)
assessin
...

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.
Designation: D5139 − 10 D5139 − 12
Standard Specification for
Sample Preparation for Qualification Testing of Coatings to
1
be Used in Nuclear Power Plants
This standard is issued under the fixed designation D5139; 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
1.1 This specification defines the size, composition, and surface preparation, and coating application variables for preparing
samples for evaluating coatings and linings over various substrates.
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical
conversions to SI units that are provided for information only and are not considered standard.
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility
of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
A36/A36M Specification for Carbon Structural Steel
C33/C33M Specification for Concrete Aggregates
C150/C150M Specification for Portland Cement
C192/C192M Practice for Making and Curing Concrete Test Specimens in the Laboratory
C260 Specification for Air-Entraining Admixtures for Concrete
C494/C494M Specification for Chemical Admixtures for Concrete
C618 Specification for Coal Fly Ash and Raw or Calcined Natural Pozzolan for Use in Concrete
D3912 Test Method for Chemical Resistance of Coatings and Linings for Use in Nuclear Power Plants
D4258 Practice for Surface Cleaning Concrete for Coating
D4259 Practice for Abrading Concrete
D4260 Practice for Liquid and Gelled Acid Etching of Concrete
D4538 Terminology Relating to Protective Coating and Lining Work for Power Generation Facilities
D4541 Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers
D7234 Test Method for Pull-Off Adhesion Strength of Coatings on Concrete Using Portable Pull-Off Adhesion Testers
3
2.2 American Concrete Institute:
ACI 308 Guide to Curing Concrete
ACI Cement and Concrete Terminology
4
2.3 American National Standards Institute (ANSI):
ANSI N5.12–1974 Protective Coatings (Paints) for the Nuclear Industry, paragraph 7.4.3
3. Terminology
3.1 Definitions—Definitions for use with this standard are shown in Terminology D4538 or other applicable standards.
3.2 Definitions of Terms Specific to This Standard:
1
This specification is under the jurisdiction of ASTM Committee D33 on Protective Coating and Lining Work for Power Generation Facilities and is the direct
responsibility of Subcommittee D33.02 on Service and Material Parameters.
Current edition approved April 15, 2010July 1, 2012. Published April 2010August 2012. Originally approved in 1990. Last previous edition approved in 20012010 as
D5139 - 90 (2001)D5139 – 10. which was withdrawn January 2010 and reinstated in April 2010. DOI: 10.1520/D5139-10.DOI: 10.1520/D5139-12.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
3
Available from American Concrete Institute (ACI), P.O. Box 9094, Farmington Hills, MI 48333-9094, http://www.concrete.org.
4
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
D5139 − 12
3.2.1 bughole (surface air void), n—a small regular or irregular cavity, usually not exceeding 1.5 mm in diameter, resulting from
entrapment of air bubbles in the surface of formed concrete during placement and consolidation (ACI Cement and Concrete
Terminology).
3.2.2 curing compound, n—a liquid that can be applied as a coating to the surface of newly placed concrete to retard the loss
of water and, in the case of pigmented compounds, to reflect heat so as to provide an opportunity for the concrete to develop its
properties in a favorable temperature and moisture environment (ACI Cement and Concrete Terminology).
4. Significance and Use
4.1 This specificat
...

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1.1 This practice covers the methodology, summarized in Annex A1, to be used in the analysis and interpretation of neutron exposure data obtained from LWR pressure vessel surveillance programs and, based on the results of that analysis, establishes a formalism to be used to evaluate present and future condition of the pressure vessel and its support structures2 (1-74).3  
1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods (see Master Matrix E706) (1, 5, 13, 48, 49).2 In order to make this practice at least partially self-contained, a moderate amount of discussion is provided in areas relating to ASTM and other documents. Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, and exposure units.  
1.3 This practice is restricted to direct applications related to surveillance programs that are established in support of the operation, licensing, and regulation of LWR nuclear power plants. Procedures and data related to the analysis, interpretation, and application of test reactor results are addressed in Practice E1006, Guide E900, and Practice E1035.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM E3105-17(2023)(Specification)
Standard Specification for Permanent Coatings Used to Mitigate Spread of Radioactive Contamination

ABSTRACT
This specification prescribes the performance criteria for non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and protect uncontaminated areas against the spread of radioactive contamination. It covers the minimum performance requirements (shelf life, adhesion, abrasion resistance, dry/cure time, decontamination factor, airborne release fraction, respirable fraction, radiation resistance) as well as the mechanical and chemical properties for permanent coatings that are intended to immobilize dispersible radioactive contamination deposited on buildings and equipment as might result from anticipated to unanticipated events to include normal operating conditions, decommissioning, and radiological release. The coating is intended to reduce: migration of the contamination into or along buildings, equipment, and other surfaces; resuspension of contamination into the air; and the spread of contamination as a result of external forces such as pedestrian traffic. It shall: be applicable to both vertical and horizontal surfaces; work within a range of environmental and radiological conditions; and be applicable to both porous and nonporous materials such as concrete, wood, metal, ceramics, and plastics. Furthermore, the coating may include constituents that will physically or chemically bind and hold radioactive contamination.
SCOPE
1.1 This specification is intended to provide a basis for identification of non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and to protect uncontaminated areas against the spread of radioactive contamination.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM E1035-18(2023)(Practice)
Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

SIGNIFICANCE AND USE
3.1 Prediction of neutron radiation effects to pressure vessel steels has long been a part of the design and operation of light water reactor power plants. Both the federal regulatory agencies (see 2.3) and national standards groups (see 2.1 and 2.2) have promulgated regulations and standards to ensure safe operation of these vessels. The support structures for pressurized water reactor vessels may also be subject to similar neutron radiation effects (1, 3-6).2 The objective of this practice is to provide guidelines for determining the neutron radiation exposures experienced by individual vessel supports.  
3.2 It is known that high-energy photons can also produce displacement damage effects that may be similar to those produced by neutrons. These effects are known to be much less at the belt line of a light water reactor pressure vessel than those induced by neutrons. The same has not been proven for all locations within vessel support structures. Therefore, it may be prudent to apply coupled neutron-photon transport methods and photon-induced displacement cross sections to determine whether gamma-induced dpa exceeds the screening level of 3.0 × 10–4 used in this practice for neutron exposures. (See 1.3.)
SCOPE
1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for:  
1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities.  
1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures.  
1.2 The values stated in SI units are to be regarded as standard; units that are not SI can be found in Terminology E170 and are to be regarded as standard. Any values in parentheses are for information only.  
1.3 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 × 1017 neutrons/cm2 or exceeds 3.0 × 10−4 dpa (1).2 (See Terminology E170.)  
1.4 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief discussion of this issue in 3.2.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. (For example, (2).)  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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