ORNL-TM-2412 Part V Contract No. W-7405-eng-26 REACTOR DIVISION DESIGN CONSIDERATIONS OF REACTOR CONTAINMENT SPRAY SYSTEMS - PART V. PROTECTIVE COATINGS TESTS J. C. Griess T. H. Row C. D. Watson G. A. West LEGAL NOTICE This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, com- pleteness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. OCTOBER \970 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee operated by UNION CARBIDE CORPORATION for the U. S. ATOMIC ENERGY COMMISSION
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ORNL-TM-2412 Part V
Contract No. W-7405-eng-26
REACTOR DIVISION
DESIGN CONSIDERATIONS OF REACTOR CONTAINMENT SPRAY SYSTEMS - PART V. PROTECTIVE COATINGS TESTS
J. C. Griess T. H. Row C. D. Watson G. A. West
L E G A L N O T I C E
This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, com-pleteness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights.
OCTOBER \970
OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee
operated by UNION CARBIDE CORPORATION
for the U. S. ATOMIC ENERGY COMMISSION
FOREWORD The Spray and Absorption Technology Program is coordinated by Oak Ridge National Laboratory for
the United States Atomic Energy Commission. The program involves research on all aspects of containment spray systems proposed for use as an engineered safety feature in pressurized water reactor containment buildings and investigations of certain aspects of the pool-pressure-suppression containment concept as applied to boiling water reactors. A document (ORNL-4360, Spray and Pool Absorption Technology Program) has recently been issued.
This document reports tests conducted to evaluate present-day protective coatings that could be applied to surfaces within a reactor containment building. The effect of temperature and spray solutions were considered in these tests. While other tests are needed to qualify a coating for use in a containment structure, these tests do indicate that present technology in the coatings industry can more than adequately produce a coating that will be useful in this application.
This is the fifth report in a series designed to present program information pertinent to actual plant design considerations. Additional reports in this series include:
T. H. Row, L. F. Parsly, H. E. Zittel, Design Considerations of Reactor Containment Spray Systems -Parti, USAEC ReportORNL-TM-2412, April 1969.
C. Stuart Patterson and William T. Humphries, Design Considerations of Reactor Containment Spray Systems - Part II. Removal of Iodine and Methyl Iodide from Air by Liquid Solutions, USAEC Report ORNL-TM-2412, Part II, August 1969. J. C. Griess and A. L. Bacarella, Design Considerations of Reactor Containment Spray Systems - Part III. The Corrosion of Materials in Spray Solutions, USAEC Report ORNL-TM-2412, Part III, December 1969.
L. F. Parsly, Design Considerations of Reactor Containment Spray Systems - Part IV. Calculation of Iodine-Water Partition Coefficients, USAEC Report ORNL-TM-2412, Part IV, January 1970.
Thomas H. Row Technical Coordinator Spray and Absorption Technology Program
i i i
CONTENTS
Foreword iii
Abstract 1
Introduction 1
Standard for Protective Coatings 2
Recirculating Loop Tests 2
Test Description 3
Protective Coating Specimens 3
Test Results 3
Tests at Carolinas-Virginia Tube Reactor 4
Test Description 4
Protective Coating Specimens 4
Test Results 5
Summary and Conclusions 5
Acknowledgment 6
v
DESIGN CONSIDERATIONS OF REACTOR CONTAINMENT SPRAY SYSTEMS - PART V. PROTECTIVE COATINGS TESTS
J. C. Griess1 C.D.Watson3
T. H. Row2 G. A. West3
ABSTRACT The research carried out in the Spray and Absorption Technology Program at ORNL has been extended to
include the evaluation of protective coatings to be used in reactor containment structures. These coatings will be subjected to the high temperature and radiation conditions possible in such containment structures following a design basis accident. Because of this possibility it is necessary to assure that the coatings are not removed in large quantities that might inhibit or negate proper operation of emergency cooling equipment.
Thirty-five different protective coatings were tested in a recirculating loop facility at ORNL, while 106 different coatings were placed in the Carolinas-Virginia Test Reactor containment building (Parr, South Carolina) and subjected to four steam system blowdown tests.
In the loop tests the coatings were examined for resistance to two proposed containment spray system solutions, 0.15 m NaOH + 0.28 m Na2S 2 0 3 , at several temperatures. The blowdown tests at CVTR also included some spraying with process water for pressure reduction.
INTRODUCTION The interior surfaces of reactor containment buildings and equipment are normally protected by
coatings (e.g., paint, which is normally sprayed on the surfaces). These coatings serve in the dual capacity of improving the aesthetic quality of the structure and of protecting the surfaces from corrosion. It is also necessary for the coatings to exhibit certain adheience characteristics under the severe environmental conditions that may exist in the building in the event of a design basis accident (DBA). The coatings cannot present a hazard to the necessary shutdown cooling equipment that must operate properly in the time period following an accident. Such a hazard would result from delamination of coatings in quantities sufficient to cause pump fouling, pipe or nozzle plugging, or fuel element coolant passage blockage.
In a pressurized water reactor (PWR) design basis accident, in which the primary system ruptures, the containment building will be subjected to a lligh-temperature (~290°F) steam-air environment and radiation. At this time, the interior of the structure is sprayed with either borated water or borated water containing other chemical additives for the purpose of sequestering fission products — iodine in particular.
In contrast, boiling water reactors (BWR) use a pressure suppression type of containment with the blowdown being directed through a pressure suppression pool. Coatings in this type of system would also be subjected to elevated temperatures and radiation.
Both PWR's and BWR's employ core spray systems as engineered safety features to provide core cooling in the event that a primary system rupture renders the normal cooling system inoperable. The core spray systems use water from the containment building sumps (PWR) or suppression pool (BWR) for a supply following the initial introduction of stored refueling water.
1 Reactor Chemistry Division. 2
Reactor Division. Chemical Technology Division.
1
2
The tests reported in this document were designed to subject the coatings to various combinations of steam, elevated temperatures, and spray solutions. No radiation exposure of the coatings was made.
The coatings were exposed in a recirculating loop facility at the ORNL Y-12 area which was used in the Spray and Absorption Technology Program4 to study the corrosive effects of spray solutions on typical materials of construction found in containment buildings.5 Coating samples were also placed in the Carolinas-Virginia Tube Reactor (CVTR) containment building during ihe In-Plant Testing Project recently conducted by Phillips Petroleum Company.6
STANDARD FOR PROTECTIVE COATINGS Review of the use of a reactor containment spray system led to the question of whether the protective
coatings (paints) used in the structure would withstand chemicals, temperature, and radiation conditions anticipated during an accident sequence. Consequently, a series of tests was planned and executed to provide the information needed to evaluate the use of coatings as well as to provide a basis for drafting a standard to be used in future applications.
Thi. standard, entitled American National Standard, Protective Coatings (Paints) for Light Water Nuclear Reactor Containment Facilities, is currently in the process of final review for approval by the American National Standards Committee N101. The standard will be conjunctive with American National St&ndard, Protective Coatings (Paints) for the Nuclear Industry, ANSI N5.9-1967. The subcommittee assembled to draft the standard represented a cross section of the industry: 3 groups involved in AEC-sponsored research, 11 coating manufacturers, 5 architectural engineering firms, 2 utilities, 3 nuclear system manufacturers, and a steel fabricator. It is felt that the standard will present a useful and practical guide for the selection and testing of coatings.
Four basic tests were outlined for use in coating evaluation:
1. fire evaluation tests,
2. thermal conductivity determination,
3. procedure? for testing coatings at simulated DBA conditions,
4. repairability and maintenance tests.
The results presented in this report involve tests in the third category, simulated DBA (design basis accident) conditions. The types of failure considered were flaking, delamination and/or peeling, blistering, and chalking as defined either by American Society for Testing and Materials Standard or by the draft standard.
RECIRCULATING LOOP TESTS The Spray and Absorption Technology Program has included research into the corrosion of
construction materials by typical spray solutions.4 '5 Coupons of representative material were exposed in a loop designed to operate at pressures up to 150 psig. The loop was equipped with an internal spray nozzle to allow for coupon exposure in a sprayed volume as well as submerged in the solution. The testing of
4 T. H. ROW, Spray and Pool Absorption Technology Program, USAEC Report ORNL-4360 (April 1965). 5 J. C. Griess and A. L. Bacarella, Design Considerations of Reactor Containment Spray Systems - Part III. The
Corrosion of Materials in Spray Solutions, USAEC Report ORNL-2412, Part III. 6 J. A. Norberg, Carolinas-Virginia Tube Reactor (CVTR) In-Plant Testing Project, USAEC Report IDO-17258H (April
1969).
3
protective coating samples was done in this same loop under the same stringent accident environment conditions.
Test Description
The test facility consisted of a stainless steel loop with a canned rotor pump to recirculate solution through a spray nozzle into a spray chamber. The spray chamber was a 52-in. length of 8-in.-ID stainless steel pipe which contained a removable rack with Teflon-insulated hooks for suspending the test specimens. In the tests described in this report, the spray chamber was operated half full of solution so that half of the specimens were exposed to the spray and half were totally submerged. All parts of the system in contact with solution weie type 304 stainless steel, and adequate heaters and coolers were provided to maintain any desired temperature. The temperature was controlled from a thermocouple immediately ahead of the spray nozzle, but the temperature throughout the system was constant within 2 to 3°C.
Two separate test campaigns using two different solutions were conducted. One solution contained 0.15 m NaOH and 0.28 m H 3B0 3 (3000 ppm boron), and the second contained the same reagents plus 0.064 m Na2S203 (1% by weight). In both cases, the pH was 9.3 ±0.1. With each solution, two specimens of each coating were exposed in the spray and two were totally submerged in the solution. The system was heated to 300°F, which required an initial heatup time of about i hr, and then the temperature was reduced according to the following schedule: 300°F for 5 min, 285°F for 1 hr 45 min, 225°F for 22 hr 15 min. After this time, the system was cooled and opened, and one of each type of specimen was removed from the spray region and one from the solution; then the test was continued for 336 hr at 150°F. After this exposure all specimens were examined and compared with the unexposed control specimen.
Protective Coating Specimens
Thirty-six different protective coatings were supplied on steel coupons by eleven different man-ufacturers, and thirty-five of these were subjected to test. In nearly all cases, nine flat specimens each 1 in. by 2 in. with a V4-in. hole at one end were received and eight of these were tested, with the ninth specimen serving as a control. Two manufacturers supplied larger test panels, and these were cut with a water-cooled abrasion cutoff wheel to approximately the same size so that they would fit conveniently on the test rack. During cutting, the entire coat peeled from one panel, and this coating was not tested. All specimens except the controls were scribed with an X to bare metal before testing, and an identification mark was stenciled on one flat surface of most specimens.
Table 1 lists the samples tested and the supplier. The figure numbers in the third column refer to subsequent photographs that show the appearance of the specimens after the test. In some cases information about the thickness and types of coatings was furnished, but in others essentially no information about the type of coating was provided.
Test Results
The general criteria for evaluation of the specimens after exposure in the test loop were tho^e set out in the standard, described in the section Standard for Protective Coatings. The types of failure considered were flaking, delamination and/or peeling, blistering, and chalking.
Some general observations were:
1. Identical specimens in the two different solutions looked the same after comparable exposure times.
4
2. The damage suffered by the coatings was the same in the spray and when totally submerged in the solution.
3. Specimens removed after the first day generally looked the same as duplicate specimens exposed for the entire period, indicating that most of the damage probably occurred at the higher temperatures. ,
Figures 1-32 are photographs of the specimens. The "results" apply equally to specimens exposed in both solutions for 1 day to 14 days.
TESTS AT CAROLINAS-VIRGINIA TUBE REACTOR
The Carolinas-Virginia Tube Reactor (CVTR) is a pressurized D 2 0 moderator and coolant reactor operated at Parr, South Carolina, by the Carolinas-Virginia Nuclear Power Associates (C VNPA). The facility has been decommissioned, and a program was established by Phillips Petroleum Company and CVNPA to provide information on containment system behavior.6 The program included containment leakage rate systems evaluation, dynamic structural vibration testing, and containment response to simulated design basis accident conditions. The containment response tests were those in which protective coating specimens were exposed.
Test Description
The CVTR containment building, a steel-lined reinforced concrete structure, was designed for accident conditions of 21 psig, 215°F, and 100% humidity. The facility is located adjacent to an older coal-fired generation station. The accident simulations were made possible by coupling the CVTR containment to the coal-fired system through appropriate valving and injecting steam into the CVTR to a preselected pressure. The steam was injected through a diffuser pipe located above the main operating floor. Four blowdowns were performed in 1969:
1. steam injection to 7.5 psig with natural pressure decay,
2. steam injection to 17.6-17.8 psig with natural pressure decay,
3. steam injection to 17.6-17.8 psig with containment spray system (295 gpm) actuation 30 sec after pressure peak,
4. steam injection to 17.6-17.8 psig with containment spray system (500 gpm) actuation 30 sec after pressure peak.
The temperature and pressure in the area of the specimens during each blowdown are shown in Figs. 33—36. The temperature was monitored by a thermocouple within V2 in. of the specimen support strips.
Protective Coating Specimens
Protective coatings applied separately to large (~6 X 6 in.) concrete and steel panels from coating firms were received at ORNL in November 1968 and transported to the CVTR for installation at the start of the blowdown series. While on the CVTR site the shipping crates were stored in a heated storage building from mid-November to mid-Mar. A complete listing of the samples by identification number and firm designation is given in Table 2. The coupons were mounted on 1-in. aluminum strips long enough to accommodate eight 6 X 6 in. samples. The location of the 23 strips used was selected at random. These strips were attached to a mounting bracket on the steel liner of the containment building approximately 6 ft above the main
5
operating floor.7 This placed the samples in the largest unobstructed free gas volume in the CVTR containment, that above the operating floor. All of the areas below this floor have compartments and equipment that would affect free movement of gases during the blowdown. Samples were exposed for all four tests except where noted.
Test Results
The specimens exposed in the CVTR tests were also evaluated on the basis of the Standard (see section Standard for Protective Coatings) failure criteria of flaking, delamination and/or peeling, blistering, and chalking.
The specimens were examined on April 28 after the second test (April 25) by Messrs. T. H. Row, ORNL, and W. L. Albrecht, TVA. Observed defects were recorded for the coded specimens, and these are listed in Table 2 by firm name and specimen identification number. Mr. J. A. Norberg of Phillips Petroleum Company examined the specimens after each test and indicated that the major defects appeared after the second test where the vessel reached 17.7 psig.
The specimens were returned to ORNL following the last test, and final observations were made at that time. The coatings were exhibited at a meeting of participating firms held at ORNL in June 3969= Photographs were taken of each group of test specimens with the unexposed control; these are presented in Figs. 37—64. Results of the tests are indicated in Table 2. (It should be noted that defects circled in the photographs were incurred in shipping.)
SUMMARY AND CONCLUSIONS
A selection of protective coatings (paints) supplied by manufacturers servicing the nuclear and utility industries were subjected to tests simulating DBA exposure conditions in light-water reactor containment facilities. Two types of tests were conducted: (1) a recirculating loop test involving the exposure of small coated steel coupons suspended in a corrosive environment of chemical solutions at various temperatures and pressures and (2) a test conducted inside the Carolinas-Virginia Test Reactor (CVTA) containment facility, involving large coated steel and concrete panels exposed to steam at various temperatures and pressures and to a water spray (without chemicals). In general, the coating systems tested could be classified in the inorganic zinc, epoxy, modified phenolic, modified epoxy, vinyl, and polyurethane generic categories.
The majority of the coatings exposed to the recirculating loop test survived the test in an acceptable fashion. Blistering (probably the result of a temperature rather than chemical attack) was the chief mode of failure. Other failures resulted from cracking, delamination, and brittleness. Discoloration occurred in many cases, but this effect in itself was not considered deleterious unless accompanied by blistering or other similar loss of film properties. Undercutting of scribed specimens occurred in only a few specimens, indicating little or no attack by the heated recirculating chemical solutions.
The CVTR tests, involving only steam (at various pressures and temperatures) and water sprays, resulted in coating failure principally by blistering, but again a very high percentage of the coatings survived the tests. The steam pressures and temperatures attained in the CVTR tests were not as high as desired to
7 J. A. Norberg and G. E. Bingham, Simulated Design Basis Accident Tests of the Carolinas-Virginia Tube Reactor Containment - Preliminary Results, USAEC Report IN-1325 (October 1969).
6
simulate a calculated DBA for many of the PWR and BWR facilities, but the results are considered very worthy guideline information.
The tests also indicate that the criteria for failure as outlined in the proposed standard (see section Standard for Protective Coatings) can be used to successfully evaluate coatings.
The results reported are in agreement with tests performed by Newby at Idaho Nuclear8-10 in support of the LOFT project.
In general, the coating systems surviving both tests fall predominantly into the following categories:
1. inorganic zinc over inorganic zinc primer,
2. epoxy over inorganic primer,
3. epoxy over epoxy primer,
4. modified epoxies and modified phenolic systems,
5. vinyl systems.
The order of listing is not related to the order in which one system excels another except possibly the vinyls. The vinyls appear to survive only in a marginal fashion, in which retention of film integrity is the exception rather than the rule.
In conclusion, the evaluation of coatings in the two test systems used resulted in a large number of promising coating systems for possible use in light-water containment facilities. In the future, these candidate coating systems and others can be further evaluated, if desired, by simple autoclave tests11 and radiation damage tests12 and the combined results used as a basis for the selection of coatings for a given reactor facility.
ACKNOWLEDGMENT
The authors would like to express our appreciation to A. L. Bacarella, of Oak Ridge National Laboratory, who assisted in conducting the tests, to J. A. Norberg, of Idaho Nuclear Corporation, whose cooperation made possible the conducting of the CVTR tests, and to the participating coating industry firms, who contributed the representative spectrum of samples which made the tests meaningful.
aB. J. Newby, Applicability of Conventional Protective Coatings to Reactor Containment Buildings, USAEC Report IN-1169 (June 1968).
9B. J. Newby, Applicability of Chemically Removable Coatings to Reactor Containment Buildings, USAEC Report IN-1170 (August 1968).
10Development of Testing Procedures for Protective Coatings to Be Used in Nuclear Reactor Containment Structures, USAEC Report IN-1253 (February 1969).
1 'Proposed American National Standard, Protective Coatings (Paints) for Light-Water Reactor Containment Facilities (N 101.5), American National Standards Institute, Inc., November 1969.
1 2 American National Standard, Protective Coatings (Paints) for the Nuclear Industry, ANSI N5.9-1967.
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Table 1. Protective Coatings Tested in the ORNL Spray Loop
T h i c k n e s s Manufacturer Identification Figure No. (mils) Proprietary Designation
Amercoat Corp. 1 1
2 2
3 3 Carboline Co. 10073-A 4
10073-B 5
10073-C 6
Celanese Coatings EP 7 Co., Devoe Paint Division CZ 8
Sandblasted; 1 coat Penn-Chem Ponamid Hi-B epoxy 53 series both sides; 2 coats one side for 8 - 1 2 mils total; glossy side, 1 coat Penn-Chem Ponamid enamel 51 series, total 5 - 8 mils
1 coat No. B44 V A21 Rex thane concrete cond. 1 coat No. B69 W 56 Rexthane white enamel 1 coat No. B42 V 2 mixing latex liquid 1 coat No. B69 W 56 Rexthane white enamel 1 coat No. B69 G 31 Kem Cati-Coat primer 7 coats No. B69 W 56 Rexthane white enamel 1 coat No. B69 A 47 zinc clad 7 3 coats No. B69 W 36 Kem Cati-Coat white enamel 1 coat No. B69 A 47 zinc clad 7 7 coats No. B69 W 56 Rexthane white enamel 1 coat No. B69 G 31 Kem Cati-Coat primer 3 coats No. B69 W 36 Kem Cati-Coat white ename!
SP-13 aluminum, air dried
SP-100 A (white and red), baked
SP-300 A (purple and red), baked
No observable damage
Small bubbles (may have occur, ed during curing)
No observable damage
No observable damage
No observable damage
to 2-in.- diam blisters on SW-2B
No observable damage
No observable damage
No observable damage
No observable damage
No observable damage
No observable damage
No observable damage
Manufacturer Identification Figure No.
Subox Division, Wyandotte Chemical Corp.
The Valspar Corp.
Wisconsin Protective Coating Corp.6
SP-4 and SP-4B 59
SP-5 and SP-5B 59
SB-land SB-IB 60
SB-2 and SB-2B 60
SB-3 and SB-3B 60
SB-4 and SB-4B 60
V-l and V-1B 61
V-2 and V-2B 61
V-3 and V-3B 61
V-4 and V-4B 62
V-5 and V-5B 62
V-6 and V-6B 62
W-l and W-1B 63
W-2 and W-2B 63
W-3 and W-3B 63
Table 2. (continued)
Thickness (mils) Proprietary Designation Results
15-18
16-19
17-21
15-18
7 - 1 0
5.5-8
7 - 1 0
12-14
9 -12
7 - 1 0
5
7
5
SP-300 (yellow and red), baked
SP-100 (white and yellow), baked
Capox EP primer Capox EP intermediate Capox EP topcoat Capox A HB primer Capox A HB intermediate Capox A HB topcoat Capox EP primer Capox EP intermediate Capox EP topcoat urethane 340 C Capox B HB primer Capox B HB intermediate Capox B HB topcoat
Fig. 5. Carboline Co. Primer: Carboweld 11, \ \ mils. Topcoat: Phenoline 368, 5 mils. P.esults: no observable damage; surface was slightly browner in Na0H-H3B05 liian in the Na0H-H3B03-Na2S203 solution.
Fig. 6. Carboline Co. Primer: Carboline 655, 4 mils. Topcoat: Fhcrioline 368. 5 mils. Results: "crowfoot" cracking, with more cracking on sides without the score mark.
Fig. 10. Con-Lux Paint Products, Inc. Primer: 1 coat Epolon AE Atomic. Topcoat: 2 coats Epolon AE 7 Atomic white. Results: large blisters; coating turned pink in Na0H-H3B03 solution; less discoloration in Na2S 20 3 solution.
Fig. 11. Con-Lux Paint Products, Inc. Primer: 1 coat Vinylgrip AE. Topcoat: 3 coats Vinyloid AE 98 Atomic white. Results: many small blisters.
Fig. 12. Keeler and Long, Inc. Results: no observable damage on either coating system.
Fig. 13. Mobil Chemical Co., No. 1. Results: some blistering on all surfaces with score marks (worse in solutions than in spray); no blisters on back side and no evidence of undercutting.
0 . 1 5 m Ba0 i f -0 .28 m H3BO3
P H O T O 95485
0 . 1 5 m Ha0H-0.28 m H 3 BO j -0 .064 B HasSjO-.,
1 d a y 300 t o 225°F
s o r c n o H
1 d a y 300 t o 2 2 5 ° ? 14 d a y s 150°F
to t o
SOLUTION
Fig. 14. Mobil Chemical Co., No. 2. Results: no observable damage.
/ i
Fig. IS. Mobil Chemical Co., No. 3. Results: coating appears brittle, since coating was cracked on side opposite stencil mark.
Fig. 16. The Sherwin-Williams Co. Primer: B69 A 47 Zinc Clad 7, 2 to 4 mils. Topcoat: B69 W 56, Rexthane white enamel, 9 to !2 mils. Results: some blistering.
Fig, 17. The Sherwin-Williams Co. Primer: B69 A 47, Zinc Clad 7, 2 to 4 mils. Topcoat: B69 W 36, Kem Cati-Coat Hi-Bild white enamel, 12 to 14 mils. Results: cracking along edges; some blistering.
Fig. 18. The Sherwin-Willians Co. Primer: B69 G 31, Kem Cati-Coat primer, 1 to 2 mils. Topcoat: B69 W 36, Kem Cati-Coat Hi-Bild white enamel, 10 to 12 mils. Results: no observable damage.
Fig. 19. The Sherwin-Williams Co. Primer: B69 G 31, Kem Cati-Coat primer, 1 to 2 mils. Topcoat: B69 W 56, Rexthane white enamel, 10 to 12 mils. Results: no observable damage.
0.15 A Ka08-0.26 a HJB03
PHOTO 95482
0.15 a Ha0H-0.28 a H3B03-0.CIS4 a & 2 S 2 0 ,
1 day 300 t o 225°F 1 dsy 300 t o 225°F
V < 5 N \ j
soianos
r * P H a>
sorcnoH
1 day 300 to 225°F 14 days 150°F
1 day 300 t o 225°F 14 days 150°F
9
<T>
SOLUTION I S H U t f l
O R I G I N A L
Fig. 20. Sperex Corp. SP-13, silicone acrylic blend, air dried. Results: aluminum color turned white; some very small "chipped-out" spots; rusty at edges and scribe marks on coupons in the Na2S203 solution.
Fig. 21. Sperex Corp. SP-100, silicone, baked. Results: slight rust spot on one specimen.
PHOTO 95499
0.15 m Ka0fr-0.28 m H3BO3 0.15 m KaOH-O.28 a H3B03-0.064 n Ua2S20j
0 . 1 5 B TFAOFT-0.28 M H 3 B 0 J - 0 . 0 6 4 A lto2S?03
1 d a y 3 0 0 t o 2 2 5 ° F
SHIAY S 0 I O T I 0 N
1 day 300 to 225°F 1 4 d a y s 1 5 0 " ?
SffiAY sournoi?
O H I G I H A I ,
Fig. 23. Valspar Industrial Division. Primer: No. 722 EZR organic zinc-rich. Topcoat: 3 coats Epi-Gard No. 60 medium gray, 7.5 to 8.5 mils. Results: some blistering.
s j O
0 . 1 5 n K a 0 H - 0 . 2 t ? m H 3 B 0 3
1 day 300 to 225 °F
SHIAY SOLUTIO:;
1 day 30C t o 225 F U d a y s 1 5 0 ° F
•PRAY SOLUTION
PHOTO 95506
0.15 m KaOS-O.SS m H3B03-0.06<i B -fe2s203
1 day 300 to 225°F
STRAY SOLCTIOK
1 day 300 t o 225°F 14 days 150°F
SPRAY SOLUTION
ORIGINAL
" O "
Fig. 24. Valspar Industrial Division. Primer: No. 722 EZR organic zinc-rich. Topcoat: 2 coats Epi-Gard No. 100 light gray, 8 to 8.5 mils. Results: coating cracked at edges; some blistering.
Fig. 25. Wisconsin Protective Coating Corp. Primer: 7155 NP, 2 to 3 mils. Topcoat: 7155 NP, 2 to 3 mils. Results: no observable damage.
Fig. 26. Wisconsin Protective Coating Corp. Primer 7155 NP, 2 to 3 mils. Topcoat: 9009, 3 to 4 mils. Results: no observable damage.
0.15 s BaOH-0.28 m H3BO3
1 day 300 t o 225°F
CERA* SOLUTION
1 day 300 t o 225°F 14. days 150°F
SH> AY SOLUTION
PHOTO 95508
0.15 a Hs0H-0.28 m BjBOj-O.OU a !to2S203
1 day 300 t o 225°F
SffiAY SOLUTION
1 day 300 t o 225°F 14 days 150°F
r ;
SPRAY SOLUTION
ORIGINAL
Fig. 27. Wisconsin Protective Coating Corp. Only coat: 7155 NP, 5 to 6 mils. Results: no observable damage.
Fig. 28. Wisconsin Protective Coating Corp. Primer: 1000, 2 to 3 mils. Topcoat: 34 W.O. 7155, 2 to 3 mils. Results: no observable damage.
Fig. 29. Wisconsin Protective Coating Coip. Primer: 1000, 2 to 3 mils. Topcoat: 34 W.O. 9009, 3 to 4 mils. Results: paint cracked at edges and some undercutting along score marks.
Fig. 30. Wyandotte Chemicals Corp., Subox Division, SBX I. Galvanox type IV (inorganic zinc), 2 ;o 3 mils; Capox B Hi-build No. 9501, 5 mils. Results: blistering and delamination of topcoat around score marks and mounting holes.
Fig- 31. Wyandotte Chemicals Corp., Subox Division, SBX II. Capox B Hi-build primer No. 9500, 5 mils; Capox B Hi-build No. 9S01, S mils. Results: no observable damage.
Fig. 32. Wyandotte Chemicals Corp., Subox Division, SBX III. Capox EP primer No. 7500, 5 mils; Cnpox EP cream No. 7501, 2 to 3 mils. Results: no observable damage.
35
Fig. 37. Amercoat Corp. Test Panels.
PHOTO 95678
j OAK RIDGE NATIONAL LABORATORY ! ' < (• f H •) m I I v ' •• l i . l i i i l i t i i i U I j J .
Fig. 38. Amercoat Corp. Test Panels.
36
PHOTO 95701
P*" OAK RIDGE NATIONAL LABORATORY 0 1 2 3 4 S 6 7 8 9 10 M « 1 • ' ' • • i ' 1 I ' > ( I ' l ' ' ' ' " ' " '• ' t • I > i • 1 • I • I • I i l . i ' i J i I J
Fig. 39. Amercoat Corp. Test Panels.
PHOTO 95704
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Fig. 40. Battelle Memorial Institute Test Panels.
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Fig. 41. Caiboline Corp. Test Panels.
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Fig. 42. Celanese Coatings Co. Test Panels.
38
PHOTO 95690
Fig. 43. Chemline Industrial Coatings Test Panels.
PHOTO 95687
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Fig. 44. Con-Lux Paint Products, Inc., Test Panels.
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PHOTO 95697
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Fig. 45. Con-Lux Paint Products, Inc., Test Panels.
PHOTO 95688
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Fig. 46. Kalman Floor Co., Inc., Tot Panels.
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Fig. 47. Kalman Floor Co., Inc., Test Panels.
Fig. 48. Keeler and Long, Inc., Test Panels.
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Fig. 49. Keelei and Long, Inc., Test Panels.
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Fig. 50. Koppeis Co. Test Panels.
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Fig. 51. NAPKO Corp. Test Panels.
PHOTO 95703
OAK RIDGE NATIONAL LABORATORY -* " S 6 7 B 9 10 M
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Fig. 52. NAPKO Corp. Test Panels.
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Fig. 53. Mobil Chemical Co. Test Panels
Fig. 54. Mobil Chemical Co. Test Panels.
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Fig. 55. Mobil Chemical Co. Test Panel*.
Fig. 56. Penrubujy Coalings Corp. Tort Panels.
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Fig. 61. The Valspar Corp. Test Panels.
PHOTO 95680
Fig. 62. The Valspar Corp. Tat Panels.
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Fig. 63. Wisconsin Protective Coating Corp. Test Panels.
Fig. 64. Wisconsin Protective Coating Corp. Test Panels.