iTeh StandardsiTeh Standards
EURUSD
Your shopping cart is empty.
ASTM

ASTM D5139-10

(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
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.
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.
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.

General Information

Status
Historical
Publication Date
14-Apr-2010
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 D5139-90(2001) - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants (Withdrawn 2010)
Effective Date
15-Apr-2010
Replaced By
ASTM D5139-12 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used 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
15-Apr-2010
Referred By
ASTM D4082-10(2023) - Standard Test Method for Effects of Gamma Radiation on Coatings for Use in Nuclear Power Plants
Effective Date
15-Apr-2010
Referred By
ASTM D8104-17(2023) - Standard Guide for Determining Coating Qualification Test Data Applicability
Effective Date
15-Apr-2010
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
15-Apr-2010
Referred By
ASTM D6943-15(2019) - Standard Practice for Immersion Testing of Industrial Protective Coatings and Linings
Effective Date
15-Apr-2010
Referred By
ASTM D5144-08(2021) - Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
Effective Date
15-Apr-2010
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
15-Apr-2010
Referred By
ASTM D8157-19 - Standard Guide for Qualification Testing of Coatings Used in Coating Service Level I in Nuclear Power Plants
Effective Date
15-Apr-2010

Buy Standard

ASTM D5139-10 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power PlantsASTM D5139-10 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants
PreviousNext
Technical specification
ASTM D5139-10 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants
English language
3 pages
sale 15% off
Preview
sale 15% off
Preview

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 −10
StandardSpecification 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 2.2 American Concrete Institute:
3
ACI 308 Guide to Curing Concrete
1.1 This specification defines the size, composition, and
surface preparation and coating application variables for pre-
3. Significance and Use
paring samples for evaluating coatings and linings over various
3.1 This specification provides uniform requirements for the
substrates.
preparation of test samples used for testing of coatings and
1.2 The values stated in inch-pound units are to be regarded
linings to be used in nuclear power plants.
as standard. The values given in parentheses are mathematical
3.2 At the users discretion, this standard may also be used
conversions to SI units that are provided for information only
when preparing samples to be tested for the purpose of
and are not considered standard.
assessing performance attributes for coating and lining systems
that may be applied in other types of power plants or for other
2. Referenced Documents
industrial facilities.
2
2.1 ASTM Standards:
A36/A36M Specification for Carbon Structural Steel
4. Steel Samples
C33/C33M Specification for Concrete Aggregates
4.1 Sample size shall be a minimum of 2-in. wide by 4-in.
C150/C150M Specification for Portland Cement
1
long by ⁄8-in. thick (50.8-mm wide by 101.6-mm long by
C192/C192M Practice for Making and Curing Concrete Test
3.175-mm thick) unless otherwise stated in the referenced test
Specimens in the Laboratory
method. Edges and corners may be rounded.Asuitably located
C260 Specification for Air-Entraining Admixtures for Con-
1
⁄4 in. (6.35 mm) diameter hole may be provided in the test
crete
panel as appropriate when required by the test method.
C494/C494M Specification for Chemical Admixtures for
4.1.1 For Test Method D4541 the minimum size shall be
Concrete
1
3-in. wide by 5-in. long by ⁄4-in. thick (76.2-mm wide by
C618 Specification for Coal Fly Ash and Raw or Calcined
127-mm long by 6.35-mm thick).
Natural Pozzolan for Use in Concrete
D3912 Test Method for Chemical Resistance of Coatings 4.2 Unless otherwise required, all panels shall be carbon
and Linings for Use in Nuclear Power Plants steel, meeting the requirements of Specification A36/A36M.
D4258 Practice for Surface Cleaning Concrete for Coating
4.3 Surface preparation criteria, including substrate cleanli-
D4259 Practice for Abrading Concrete
ness and profile, shall be specified.
D4260 Practice for Liquid and Gelled Acid Etching of
Concrete
5. Concrete Blocks
D4541 Test Method for Pull-Off Strength of Coatings Using
5.1 The minimum size shall be 2-in. by 2-in. deep by 4-in.
Portable Adhesion Testers
long (50.8-mm by 50.8-mm deep by 101.6-mm long) unless
otherwise stated in the referenced test method. The edges may
1
be chamfered up to ⁄4 in. (6.35 mm) maximum.
1
This specification is under the jurisdiction of ASTM Committee D33 on
ProtectiveCoatingandLiningWorkforPowerGenerationFacilitiesandisthedirect 5.2 Composition shall be as follows:
responsibility of Subcommittee D33.02 on Service and Material Parameters.
3
Cement Specification C150/C150M, 7 sacks/yd
Current edition approved April 15, 2010. Published April 2010. Originally
Type II
approved in 1990. Last previous edition approved in 2001 as D5139 - 90 (2001)
Gravel Specification C33/C33M, 45 % by volume
which was withdrawn January 2010 and reinstated in April 2010. DOI: 10.1520/
3
size ⁄8 in.
D5139-10.
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
3
Standards volume information, refer to the standard’s Document Summary page on Available fromAmerican Concrete Institute (ACI), P.O. Box 9094, Farmington
the ASTM website. Hills, MI 48333-9094, http://www.concrete.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
D5139−10
7.2 Concrete:
Sand Specification C33/C33M 55 % by volume
Air-entraining Specification C260 As recommended
7.2.1 Surface preparation parameters shall be established.
admixture 4to7%
7.2.2 Users of this standard may identify project specific
Water-reducing Specification C494/C494M As recommended
admixture conditions, for example, configuration, texture, bugholes, etc.
Pozzolan Specification C618 As recommended
These conditions shall be re
...

Questions, Comments and Discussion

Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.

This May Also Interest You

ASTM
ASTM D8104-17(2023)(Guide)
Standard Guide for Determining Coating Qualification Test Data Applicability

SIGNIFICANCE AND USE
4.1 For conformance with the intent of the criteria listed in 2.2 and 2.3, coating qualification tests are founded on plant-specific test parameters that realistically reflect or bound the material and process variables that can reasonably be expected to influence qualification testing performance.  
4.2 This guide provides guidance for evaluating existing coating system qualification data for applicability to the nuclear plant desiring to use a coating system not previously used in the plant or to qualify an existing coating system.  
4.3 It is recognized that new-build plants, as well as small modular reactors currently under development, may have design features that differ from those of the operating plants that formed the basis for the existing test data. Therefore, careful review is required to assure that coating performance requirements critical to the new design are adequately addressed in the existing data or the need for additional coating testing is identified.
SCOPE
1.1 The purpose of this guide is to identify evaluation variables that can be used to determine whether existing coating qualification test data (for example, design basis accident or DBA, chemical resistance, fire resistance, thermal conductivity, etc.) meet the respective nuclear power plant qualification requirements or whether requalification is required. Guidance on developing a coating qualification test plan/procedure to qualify a new coating is beyond the scope of this standard.  
1.2 This guide is intended for use in new construction and for refurbishing existing coating systems applied to concrete and metal substrates within containment.  
1.3 This guide is intended for the use by, or under the supervision of, a person knowledgeable in coating technology and coatings used in CSL I applications, such as a person meeting the requirements of Guide D7108 or equivalent.  
1.4 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.  
1.5 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.  
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.

  • Guide
    6 pages
    English language
    sale 15% off
ASTM
ASTM D5163-16(2021)(Guide)
Standard Guide for Establishing a Program for Condition Assessment of Coating Service Level I Coating Systems in Nuclear Power Plants

SIGNIFICANCE AND USE
4.1 Establishment of an in-service coatings monitoring program permits planning and prioritization of coatings maintenance work as needed to maintain coating integrity and performance in nuclear CSL I coating systems. For additional information on nuclear maintenance coating work, refer to ASTM MNL8.4  
4.2 A coatings monitoring program enables early identification and detection of potential problems in coating systems. Some CSL I coating systems may be known in advance to be suspect, deficient, or unqualified. Monitoring coating performance will assist in developing follow-up procedures to resolve any significant deficiency relative to coating work.  
4.3 Degraded coatings may generate debris under design basis accident conditions that could adversely affect the performance of the post-accident safety systems. A coatings monitoring program may be required to fulfill safety analysis report and generic letter commitments for CSL I coating work in a nuclear power plant facility.
SCOPE
1.1 This standard covers procedures for establishing a monitoring program for condition assessment of Coating Service Level (CSL) I coating systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition and performance of the in-service coating systems.  
1.2 It is the intent of this standard to provide a recommended basis for establishing a coatings condition assessment program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this standard may be appropriate for each operating nuclear power plant depending on their licensing commitments.  
1.3 This requirements of ASME Section XI, In-Service Inspection Subsections IWE and IWL are beyond the scope of this standard.  
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.

  • Guide
    5 pages
    English language
    sale 15% off
ASTM
ASTM D7491-21(Guide)
Standard Guide for Management of Non-Conforming Coatings in Coating Service Level I Areas of Nuclear Power Plants

SIGNIFICANCE AND USE
5.1 There are several methods for managing non-conforming coatings in an operating nuclear power plant. This guide outlines methods that have been determined to be acceptable to the nuclear industry.  
5.2 Managing the amount of non-conforming coatings is key to ensuring the amount assumed, in the licensing bases is not exceeded.  
5.3 EPRI Report 1019157 provides additional information on the selection, application, inspection and maintenance of nuclear plant safety-related protective coatings. This reference offers a detailed discussion of important considerations related to protective coatings and can be used to supplement this guide as deemed necessary.
SCOPE
1.1 This guide provides the user with guidance on developing a program for managing non-conforming coatings in Coating Service Level I areas of a nuclear power plant.  
1.2 Non-conforming coatings include degraded qualified or acceptable coatings, unqualified coatings, unknown coatings, and unacceptable coatings.  
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.

  • Guide
    4 pages
    English language
    sale 15% off
  • Guide
    4 pages
    English language
    sale 15% off
ASTM
ASTM D5139-19(Specification)
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, 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.

  • Technical specification
    4 pages
    English language
    sale 15% off
  • Technical specification
    4 pages
    English language
    sale 15% off
ASTM
ASTM D7108-12(2018)(Guide)
Standard Guide for Establishing Qualifications for a Nuclear Coatings Specialist

SIGNIFICANCE AND USE
4.1 This guide applies to personnel technically responsible for the safety-related coatings program.  
4.2 It is the responsibility of each nuclear facility or organization participating in a safety-related coatings program to ensure that only those personnel within their respective organizations who meet the requirements of this guide are designated as Nuclear Coatings Specialists.
SCOPE
1.1 This guide delineates recommendations for development of procedures and criteria for designation of an individual as a Nuclear Coatings Specialist involved in coating work in nuclear facilities. The Nuclear Coatings Specialist is responsible for the technical aspects of the safety-related coatings program in a nuclear facility or organization, which includes establishing processes and quality control requirements.  
1.2 This guide details the guidance provided in Guide D5144, and EPRI Report 1019157.  
1.3 It is the intent of this guide to provide several alternatives for designation of personnel as Nuclear Coatings Specialists.  
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.

  • Guide
    3 pages
    English language
    sale 15% off
ASTM
ASTM D5498-12a(2018)(Guide)
Standard Guide for Developing a Training Program for Personnel Performing Coating and Lining Work Inspection for Nuclear Facilities

SIGNIFICANCE AND USE
4.1 Personnel trained for coating and lining work inspection are required to perform examination/inspection tasks to verify conformance of coating and lining work to written requirements.  
4.2 This guide provides guidance for development of an indoctrination and training program for training of personnel performing coating and lining work inspection.  
4.3 Certification/qualification of personnel performing coating and lining work inspection is addressed in Guide D4537.
SCOPE
1.1 This guide is intended to assist those responsible for developing a program for the indoctrination and training of personnel performing coating and lining inspection work for nuclear facilities.  
1.2 It is recognized that organizations and job responsibilities vary widely among utilities and also among various support and service companies. It is the responsibility of the user of this guide to identify the appropriate subject matter for its program and its specific needs.  
1.3 Users of this guide must ensure that coating and lining work complies not only with this guide, but also with the licensee's plant-specific quality assurance program and licensing commitments.  
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.

  • Guide
    4 pages
    English language
    sale 15% off
ASTM
ASTM D7167-12(2018)(Guide)
Standard Guide for Establishing Procedures to Monitor the Performance of Safety-Related Coating Service Level III Lining Systems in an Operating Nuclear Power Plant

SIGNIFICANCE AND USE
4.1 Establishment of an in-service linings monitoring program permits planning and prioritization of lining maintenance work as needed to maintain lining integrity and performance in nuclear Coating Service Level III systems. Refer to ASTM MNL-8, Manual on Maintenance Coatings for Nuclear Power Plants,7 and Guide D7230, which provides guidance for selecting lining materials for new construction or maintenance of safety-related lining systems.  
4.2 A linings monitoring program enables early identification and detection of potential problems in lining systems. Some Coating Service Level III lining systems may be known in advance to be suspect, deficient, or degraded. Monitoring lining performance will assist in developing follow-up procedures to resolve any significant deficiency relative to lining work.  
4.3 Degraded linings may generate debris under normal operation and testing or during upset conditions that could adversely affect the performance of safety-related systems. In most cases, the consequence of the debris generation is flow blockage, essential heat transfer reduction, or both; ultimately leading to degradation of equipment or system performance. A linings monitoring program may be required to fulfill licensing commitments for Coating Service Level III lining work.
SCOPE
1.1 This guide covers procedures for establishing a program to monitor the performance of Coating Service Level III lining (and coating) systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition of the in-service lining systems.  
1.2 Coating Service Level III lining systems subject to this guide are generally those applied to metal substrates comprising raw water, condensate-quality water, or fuel oil wetted (that is, full or intermittent immersion) surfaces in systems that may include:  
1.2.1 Service water piping upstream of safety-related components,  
1.2.2 Service water pump internals (draft tube, volutes, and diffusers),  
1.2.3 Service water heat exchangers including the channels, pass partitions, tubesheets, end bells, and covers  
1.2.4 Service water strainers,  
1.2.5 Reactor water storage tanks (RWSTs),  
1.2.6 Refuel cavity water storage tanks,  
1.2.7 Reactor makeup water system,  
1.2.8 Component cooling water system,  
1.2.9 Lube oil tanks for safety-related equipment, and  
1.2.10 Emergency diesel fuel oil system.  
1.3 It is the intent of this guide to provide a recommended basis for establishing a linings monitoring program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this guide may be appropriate for any given operating nuclear power plant depending on its licensing commitments. Similar guidelines may be applicable for certain Coating Service Level II applications such as fluid immersion systems.  
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.

  • Guide
    6 pages
    English language
    sale 15% off
ASTM
ASTM E853-23(Practice)
Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results

SIGNIFICANCE AND USE
3.1 The objectives of a reactor vessel surveillance program are twofold. The first requirement of the program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region resulting from exposure to neutron irradiation and the thermal environment. The second requirement is to make use of the data obtained from the surveillance program to determine the conditions under which the vessel can be operated throughout its service life.  
3.1.1 To satisfy the first requirement of 3.1, the tasks to be carried out are straightforward. Each of the irradiation capsules that comprise the surveillance program may be treated as a separate experiment. The goal is to define and carry to completion a dosimetry program that will, a posteriori, describe the neutron field to which the material test specimens were exposed. The resultant information will then become part of a database applicable in a stricter sense to the specific plant from which the capsule was removed, but also in a broader sense to the industry as a whole.  
3.1.2 To satisfy the second requirement of 3.1, the tasks to be carried out are somewhat complex. The objective is to describe accurately the neutron field to which the pressure vessel itself will be exposed over its service life. This description of the neutron field must include spatial gradients within the vessel wall. Therefore, heavy emphasis must be placed on the use of neutron transport techniques as well as on the choice of a design basis for the computations. Since a given surveillance capsule measurement, particularly one obtained early in plant life, is not necessarily representative of long-term reactor operation, a simple normalization of neutron transport calculations to dosimetry data from a given capsule may not be appropriate (1-67).  
3.2 The objectives and requirements of a reactor vessel's support structure's surveillance program are much less stringent, and at present, are limited to ...
SCOPE
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.

  • Standard
    9 pages
    English language
    sale 15% off
  • Standard
    9 pages
    English language
    sale 15% off
ASTM
ASTM E3104-17(2023)(Specification)
Standard Specification for Strippable and Removable Coatings to Mitigate Spread of Radioactive Contamination

ABSTRACT
This specification prescribes the performance criteria for strippable/removable coatings used in immobilizing radioactive contamination, minimizing worker exposure, and facilitating subsequent decontamination or protecting uncontaminated areas against the spread of radioactive contamination. It covers the minimum performance requirements (shelf life, tensile strength, adhesion, abrasion resistance, dry/cure time, decontamination factor, airborne release fraction) as well as the mechanical and chemical properties for strippable/removable coatings. The strippable/removable coating is intended to reduce: migration of the radioactive contamination into or along buildings, equipment, and other surfaces; resuspension of contamination into the air and the airborne intake hazards of the contamination; and the spread of contamination as a result of external forces such as pedestrian traffic. The strippable/removable coating shall: be applicable to both vertical and horizontal surfaces; work within a range of environmental and radiological conditions; and be readily applied to both porous and nonporous materials such as concrete, wood, metal, ceramics, and plastics. Furthermore, the strippable/removable coating may include constituents that will physically or chemically bind and immobilize radioactive contamination.
SCOPE
1.1 This specification is intended to provide a basis for identification of strippable/removable materials used to immobilize radioactive contamination, minimize worker exposure, and facilitate subsequent decontamination or 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.

  • Technical specification
    3 pages
    English language
    sale 15% off
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.

  • Technical specification
    3 pages
    English language
    sale 15% off