ASTM D3911-95

NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
Designation: D 3911 – 95
AMERICAN SOCIETY FOR TESTING AND MATERIALS
100 Barr Harbor Dr., West Conshohocken, PA 19428
Reprinted from the Annual Book of ASTM Standards. Copyright ASTM
Standard Test Method for
Evaluating Coatings Used in Light-Water Nuclear Power
Plants at Simulated Design Basis Accident (DBA)
Conditions
This standard is issued under the fixed designation D 3911; 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.
INTRODUCTION
During a design basis accident (DBA) in nuclear power plants, conditions in the reactor containment
will be characterized by elevated temperature and pressure, as well as the presence of a radiation
environment. Water sprays, with or without chemical additives, may be used in the primary
containment to suppress the consequences of the incident, to scavenge radioactive products, and to
return the containment to near-ambient conditions.
1. Scope 3.1.1 blistering—the formation of bubbles in a coating
(paint) film.
1.1 This test method establishes procedures for evaluating
3.1.2 boiling water reactor (BWR)—a reactor in which the
protective coating systems test specimens under simulated
water moderator-coolant is boiled directly within the reactor
DBA conditions. Included are a description of conditions and
core. The pressure in the reactor vessel is only slightly greater
apparatus for temperature-pressure testing, conditions for ra-
than the steam turbine pressure.
diation testing, and procedures for preparing, examining, and
3.1.3 chemical spray—a solution of chemicals, such as
evaluating the samples.
those contained in Table 1, which could be used during a loss
1.2 The values stated in inch-pound units are to be regarded
of coolant accident (LOCA) to suppress the incident, to
as the standard. The values given in parentheses are for
scavenge fission products, and to return the facility to near-
information only.
ambient conditions.
1.3 This standard does not purport to address all of the
3.1.4 coating (paint) system—a polymeric protective film
safety concerns, if any, associated with its use. It is the
consisting of one or more coats applied in a predetermined
responsibility of the user of this standard to establish appro-
order by prescribed methods to a defined substrate.
priate safety and health practices and determine the applica-
3.1.5 cracking—a break or a split in the coating (paint)
bility of regulatory limitations prior to use.
system extending through the film or to the substrate.
2. Referenced Documents
3.1.6 curing—the transformation of a coating or other
material into a solid phase or film.
2.1 ASTM Standards:
3.1.7 DBA—a generic term for any one of a family of
D 714 Test Method for Evaluating Degree of Blistering of
accident conditions which can result from postulated events.
Paints
These conditions are generally associated with the rupture of
D 4082 Test Method for Effects of Radiation on Coatings
high energy piping. The more commonly recognized accident
Used in Light-Water Nuclear Power Plants
conditions used to evaluate coating systems for primary
D 5139 Specification for Sample Preparation for Qualifica-
containment are the LOCA or main steam pipe break.
tion Testing of Coatings to be Used in Nuclear Power
3.1.8 deionized water—water prepared by an ion exchange
Plants
process meeting the requirements of Specification D 1193,
3. Terminology
Types II and III.
3.1.9 delamination—separation of one coat or layer from
3.1 Definitions:
another coat or layer, or from the substrate.
3.1.10 engineered safety system—a system designed to
This method is under the jurisdiction of ASTM Committee D-33 on Protective
mitigate the effects of a design basis accident.
Coating and Lining Work for Power Generation Facilities and is the direct
3.1.11 irradiation—exposure to ionizing radiation.
responsibility of Subcommittee D33.02 on Service and Material Parameters.
Current edition approved Oct. 10, 1995. Published December 1995. Originally 3.1.12 light-water nuclear reactor—an apparatus, using
published as D 3911 – 80. Last previous edition D 3911 – 89.
light water as a moderator, in which fissionable material is
Annual Book of ASTM Standards, Vol 06.01.
arrayed so that controlled nuclear fission may be sustained in a
Annual Book of ASTM Standards, Vol 06.02.
NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
D 3911
TABLE 1 Typical Spray Solutions
that are corrosion-resistant to the test solutions.
Composition Chemical Compound Concentration (in Deionized Water) 5.2 The equipment shall be capable of reproducing and
continuously recording the temperature and pressure profiles of
A Sodium borate 2000 to 4000 ppm boron
Sodium hydroxide adjust solution to pH 9.0 to 10.0
the DBA conditions.
B Boric acid 2000 to 4000 ppm boron
5.3 A sufficient number of thermocouples shall be located in
Hydrazine 50 ppm unreacted excess
the test chamber to assure conformity to the test curve, and so
Sodium phosphate, dibasic adjust solution pH to 6.8 to 10.0
that both the temperature of the vapor phase and of the liquid
phase (if present) can be recorded.
self-supporting chain reaction.
3.1.13 LOCA—the specific conditions anticipated following
6. Preparation of Test Specimens
a loss of coolant accident that would expose the coated surface
6.1 Determine the appearance of the test panels prior to
of the containments of a light-water nuclear power facility to
testing by photo documentation or equivalent methods in order
the temperature-pressure environmental parameters described.
to provide a basis for post-test comparison. The testing
3.1.14 peeling—separation of one or more coats or layers of
requirements should indicate if this assessment will be done
a coating from the substrate.
prior to shipping to the test facility.
3.1.15 pressurized-water reactor (PWR)—a nuclear power
6.2 Unless otherwise specified, a minimum of four samples
reactor design utilizing liquid water under high pressure as
shall be required to establish conformance of a given coating
moderator-coolant.
system on a given substrate, with two of the four samples being
3.1.16 quality assurance—the verification of the conform-
irradiated prior to testing in accordance with Test Method
ance of materials and methods of application to the governing
D 4082. Typical laboratory test specimens are 2 by 4 by ⁄8 in.
specifications, in order to achieve the desired result.
(5.1 by 10.2 by 0.32 cm) for steel panels and 2 by 2 by 4 in.
3.1.17 reactor containment (containment)—the enclosure
(5.1 by 5.1 by 10.2 cm) for concrete blocks.
provided to protect the environment from the consequences of
6.2.1 Steel Panels—Prepare in accordance with Specifica-
a nuclear incident.
tion D 5139 or as necessary to duplicate actual conditions.
4. Significance and Use
6.2.2 Concrete Blocks—Prepare in accordance with Speci-
fication D 5139 or as necessary to
...