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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs 1999-09-07
[Table view] Category:TEST REPORT
MONTHYEARML20216G6371997-09-23023 September 1997 ANO Unit 1 SG Tube Exam ML20216H9461997-09-0808 September 1997 Cycle 13 Startup Rept ML20101H8201992-04-30030 April 1992 Reactor Containment Bldg Integrated Leakage Rate Test Rept, for Apr 1992 ML20086J0771991-11-0707 November 1991 Simulator Performance Testing Rept ML20077G9801991-04-30030 April 1991 One,Unit II Reactor Containment Bldg Integrated Leakage Rate Test ML20059E7901990-01-22022 January 1990 ASTM E-72 Load Testing of 2-h Solid Stud Wall ML20247E8271988-11-30030 November 1988 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20155D4931988-05-20020 May 1988 Rev 1 to Reactor Containment Bldg Integrated Leak Rate Test,880501 ML20214K3641986-11-24024 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `B' Pump Case-Surface Flaw ML20214K3951986-11-24024 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `A' Pump Case - Supplementary Topics ML20214K3291986-11-18018 November 1986 Rev 0 to Arkansas Nuclear One,Unit 1 Pump Case - Crack Growth Due to Transients ML20213F4731986-11-0707 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One-1 a Pump Case Indication ML20213F4791986-11-0707 November 1986 Rev 1 to Arkansas Nuclear One-1 Pump Case Stresses ML20214K3161986-11-0707 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `B' Pump Case Indication ML20206T3181986-01-31031 January 1986 Vols I-III of IEEE 634-1978 Std Cable Penetration Fire Stop Qualification Test:Arkansas Nuclear Units 1 & 2, Russellville,Ar - Site Specific,Arkansas Power & Light Co Spec APL-2434, Final Rept ML20203A2311985-10-23023 October 1985 Corrosion Test of Mechanically Sleeved Unit 1 Once-Through Steam Generator Tube ML20099M3031985-01-31031 January 1985 Rev 1 to Nonproprietary Phase I of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Program Test Series Summary Rept ML20215B4391985-01-14014 January 1985 Rev 0 to Pistar Computer Program Verification Document Program Version 3.3.1 ML20112F7681984-12-31031 December 1984 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20128K3561984-12-17017 December 1984 Change Notice 1 to Primary Reactor Containment Integrated Leak Rate Test,Final Rept ML20215B5081984-11-0909 November 1984 Rev 1 to Gensap Program Verification Document Program Version 4.0 ML20096D8011984-08-31031 August 1984 Nonproprietary Final Rept of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Confirmatory Test Program ML20203A1971984-08-0909 August 1984 Rept of Once-Through Steam Generator Mechanical Sleeve 40% Wall Reduction Test 2CAN068408, Unit Two Cycle Four Startup Rept, for Period Ending 8403151984-03-15015 March 1984 Unit Two Cycle Four Startup Rept, for Period Ending 840315 ML20215B5681983-11-19019 November 1983 Computer Program Verification - Stardyne -3 DEC01/82A H Level Ncsi Cyber 730 ML20080T8391983-06-10010 June 1983 Exam of Once-Through Steam Generator Tubes B73-8 & B112-19 from ANO-1, Final Rept ML20071G1921983-05-12012 May 1983 Station,Unit 2,Cycle Three Startup Rept, for Period Ending 830104 ML20072P8111983-03-17017 March 1983 Cycle 2 Refueling Outage Fuel Exam Results ML20215B5451982-11-24024 November 1982 Suppl a to Rev 0 to Gensap Verification. Baseplate II Verification Rept Encl ML20215B5301982-10-23023 October 1982 Rev 0 to Gensap Program Verification ML19350F1251981-06-30030 June 1981 Nonproprietary Version of Reactor Vessel Open Core Flow Model Test Rept. ML19277A0681981-06-16016 June 1981 Nonproprietary Version of Cpc/Ceac Sys Phase II Software Verification Test Rept. ML20009G3181981-06-12012 June 1981 Inservice Testing AND-Unit 1,Check Valve Reliability Analysis. ML20079F9071981-06-0202 June 1981 Nonproprietary ANO-2 Cycle 1 Refueling Outage Fuel Exam Results ML20004C5111981-05-31031 May 1981 B&W Post-Test Evaluation of Loft Test L3-1. ML20004C5161981-05-20020 May 1981 B&W Post-Test Analysis for Semiscale Test S-07-10D. ML20126K9701981-02-25025 February 1981 Primary Reactor Containment Integrated Leakage Rate Test ML20053E9161980-12-12012 December 1980 Rept on Floor & Wall Penetration Fire Stops. ML20003E6161980-10-31031 October 1980 Cesec Simulation of NSSS Transients Tests at AR Nuclear One-Unit 2. ML20151A3841980-07-28028 July 1980 Revision a to Electrical Wire & Cable Isolation Barrier Matls Test for Susquehanna Steam Electric Station,Units 1 & 2 for Bechtel Power Corp ML19323H2841980-04-30030 April 1980 AR Nuclear 1 Steam Electric Station,Unit 2,Startup Rept, Suppl 3 for Period Ending 800430 ML19318C3421980-04-30030 April 1980 Rept on Wall Penetration Fire Stops. ML19344D2581980-01-29029 January 1980 Startup Rept,Suppl 2 for Period Ending 800129. ML19260C3601979-12-17017 December 1979 Pages S1-47,S1-48,S1-A1 & S1-A2 to 791211 Suppl to Startup Rept ML19256G5611979-12-17017 December 1979 Four Pages Omitted from 791211 Submittal of Suppl 1 to 790913 Startup Rept ML19210E2641979-11-29029 November 1979 Revised Pages to Startup Rept Cycle 4 Correcting Error in Moderator Coefficient Extrapolated to 95% Full Power & Indicating Location of in-core Instrumentation Used to Determine Core Power Distribution ML19211A2891979-10-31031 October 1979 Suppl 1 to Startup Rept for Period Ending 791031 ML19209A5141979-09-25025 September 1979 Cycle 4 Startup Rept for Period Ending 790704 ML19208A9361979-07-31031 July 1979 Startup Rept. ML19344A6631979-05-14014 May 1979 Class IE Prequalification Tests for Itt Barton Pressure Differential Switch,Model 580. 1997-09-08
[Table view] |
Text
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- CHEMISTRY & CORROSION, ARC ...,..
G. J. THEUS Cust*
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I8M - RUPTURE TESTS OF INTENTIONALLY DAMGED ALLOY 600 LT56 TIBING I OCT08ER 4, 1977 v ~ - . - . -,
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SU44ARY A :ee: ra jru- : .1eress t he effe:'t .l vari us defects in A::oy C::
e:ca acncratcr taina we carried cu: at t he A :
Y .~he rN;ra xnrie:ed :f a ceries of burs: tests of defe.-ted tubin.: ueiru k TE~ pa:ite a::er :: C ':"! A th ; resswre ? ctmen :00: .:nd b:.' rei.
7:~':crtice :l hr J.rx:p i Jee a: (02*F x rs a:s: de tsmined.
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N N
D Distribution (COWANY L IMITED) This information is freely availeble to all N Comoany personnel . Written approval by sponsoring unit's R&D coordinator is required only if release outside of the Coreany is requested.
P. 5. Ayres - ARC G. Musat - ARC N M. J. Bell - NPGD, Lynchburg F. J. Pocock - ARC R. U. Blaser - ARC P. E . Sene met er - ARC
\q N
F. R. Curke - NPGD, Lynchburo T. 5. Sprague/L. E. Spr/ - NED Barbertor E. E. Coulter - NEC, barberton H. 5. Swenson ARC N H. F. Dobel - MPGD. Lynchburg G. F. Tisinai - Beaver Falls
' Chemistry & Corrosion files (3)
H . A . Dossi a n - AR C
\ R. M. Douglass - Mt. Vernon Corporate Information Services G. h. Esenanuel - Mt. Vernon ARC Library (3)
% D. W. Koch - NED, Barberter. WPU L tbrary ici J. A. Manzi/E. M. Dorsey - ARC B. h. Mcdonald - MPGD. Lynchbura
\ T. A. McNary 8611170249 861031 PDR ADOCK 05000313 R. C. Ritschart!/J. V. Monter - ARC P PDR j
I B&W ma kes no warranty or repr esentation, empressed or implied e with respect to the accuracy. completeness, of usefulness of the infortnat'on contained in this report e that the use of any information, apparatus, method, or process disclosed in this report rnay not infringe privately owned rights.
B&W assumes no liability with respect to the use of, or for damages resulting f rom the use of eany inf ormation, apparatus, met t N, or process disclosed in this report e experimental apparatus f urnished with this report.
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The Alloy 600 tubing in steam generators may be affected by various damaging events. The tube wall may be worn if there is movement between the support plates and tubes. Intergranular stress corrosion cracking, or wastage attack of the tees may result from upsets in weter chemistry.
~
Fatigue or other, as yet unidentified, mechanisms may also cause tee damage Should any of these events occur, it could pose a safety-related question if a main steam line break (MSLB) should subsequently occur with the loss of sesondary side pressure. The damaged tubes would have to withstand the entire primry coolant pressure (approximately 2500 psi) without rupturing. Therefore.
the purpcse of this prograr was to determine the extent of damage a tube can endure and still perfore satisfactorily in case of such an event.
I In order to establish the extent of
- allowable" tube damage, a test program was conducted wherein intentionally daanged Alloy 600 OT56 tubes were subjected to various internal pressures. The specific objective
. of the test program was to deterrine whether or not tubes dessoed to 50%
of their wall thickness could withstand a MSLB incident. For coupleteness l of the test program, 600*F tensile properties of the damaged tubes were also determined. The results of a sirilar program on the collapse strength of intentionally damaged tubes in the event of a loss of coolant accident (LOCA) have already been reported.III
- 2. TEST PROGRAM 2.1 MTERIAL The material used was Alloy 600 OTSG tubing. Heat M5442, manufactured by t- Tubular Products Division of the Babcock & Wilcon Company. All tubing was stress relieved, ll50*F/18 hours, prior to testing. The actual dimensions of this tubing are 0.628' 00 x 0.038' wall. The analysis is )
given ir Table 1.
J
Babcock &WWoom LR:77:2M1-71:1 Paem 3 Table 1. Analysis of Heat M5442 C .051 Cr 15.81 Fe 8.92 Mn .37 N1 74.01 Mg .037 5 .0063 Mo .07 Al .28 B .0018 Cu .02 Ti .25 Si .13 Co .045 Pb <.005 2.2 SPE CIME N5 Specimens were 6 in. long for rupture tests and 23 in. long for tensile tests. Defects were placed in the middle of the rupture test specimens. Defects in the tensile test specimens were placed in a location on the tube corresponding to the center of the tensile test furnace. The rupture test specimens were plugged at each end with Alloy 600 material. Alloy 600 tubing,1/4 in. 00,was inserted into a hole drilled in each end of the plug so pressurizing water could enter the specimen.
Undamaged tubes were used as comparison specimens in both rupture and tensile tests.
2.3 D_EFECT DEPTH The objective of the program is to assure satisfactory tube performance in case of an 'tSLB with tubes damaged such that only 50% of their wall rernained. Tubes with defect depths greater than 50% of the wall were tested to establish the relationship of defect depth and defect shape with rupture pressure. Tubes with defect depths less than 50% of the remaining wall were tested to coaclete the test array.
. _0
o M&h L A:77:!M1-71:1 Paan 4 The defect depths used for each defect geometry were:
- 1) 1001(0.038") of tdHe well roamining (no defect)
- 2) 751 (0.0285*) of tube wall remaining
- 3) 501 (0.019") of tube wall remaining
- 4) y)t (0.0114") of tube wall remaining 2.4 DEFECT GEOMETRY l
Mc specimen of each defect gemetry/ defect depth costination of interest was tested in the rupture test and in the 600*F tensile test.
The various defect types are described and illustrated below.
i e Longitudinal Slit A longitudinal groove 0.010" wide and I" long, was machined in the outside surface of the tube with a milling cutter. This defect simulated a longitudinal crack in the tube wall.
e 120* Circeferential Slit A slit defect groove. 0.010" wide and extending around 120" of the circaference was machined in the outside surface of the tube with a milling cutter. This defect simulated a partial cirewferential crack in the tube wall.
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N'h LR:77:!M1-71:1 Pese 5 e 360' Circumferential Slit A slit defect groove. 0.010" wide and extending completely around the circumference was :.a:hined in the outside sur' ace of a tee with a milling cutter. This defect simulated a couplete circumferential crack in the tube wall.
o Circumferential Thinning A 360* area of uniform thinning. 0.5" wide, was machiped on the outside surface of the tube. This defect simulated an area of uniforr thinning of the tube wall.
E e Flat Defect A flat spot, 0.75" long, was introduced on the tse well by machining o+ the metal . This defect simulated areas thinned by sechanical wear.
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- . . _ _ _ _ _ _ _ _ _ _ . ___ _ _______ ___ -_ _U
Butxed C -- LR:77:tyl.71:1 Paet 6 2.5 TEST ConDIT1016_
8tupture Tests Each rupture test was conducted at 600*F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at each pressure which varied, in 500 pst increments, between 1000 psi and 5000 psi.
The tubular specimens were pressurized with water of 0TSG feeesater qality (Table :).
Table 2. Pressurizing Water Chemistry pH 9 25*C 9.3-9.5 (IsH3 )
Conduc tivi ty 4-10 u shos/cm Oxygen 0 (residual hydrazine)
Iron <5 ppb Tempera tcre 600*F (316*C)
Prior to testing, the diameter of each specimen was measured at four points (45* apart) on the circumference at the site of the defect.
The specimens were then installed in a specially designed test fixture (Figure 1) which was placed into an autoclave. After the test fixture was secured in the autoclave, water was pumped into the specimens through the 1/4" 00 Alloy 600 tubino to a static pressure of 1000 psi. The temperature of the autoclave was raised to 600*F and the specimens held under these conditions for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the pressure was l
raised to 1500 psi and held fo- another 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This procedure was repeated at 500 psi increments until 5000 psi was attained. In the case of specimen failure, that specimen was valved off from the rest of the specimens and testing proceeded.
1
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Babco_ck& Wdcox L p : 77 : 2341- 71 :1 Page 7
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Babcock & h LR:77:r M1 71:1 Paae 8 At the end of the test (after 5000 psi for 24 howrs), the specimens were removed from the fixture and rammasured at the same locations as previously described to determine swelling.
Tensile Tests All tensile tests were done in accordance Wth ASTM designation E21-70. Elevated Teeperature Tensile Tests of Metallic Materials.
- 3. RESULTS AND DISCUSSION Rupture Tests i
Rupture test results are summarized in Table 3.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ' " ' ' = ^ - - 4 , _
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LA:77:fM1 71:1 y- to Table 3. Tube Retre tota (0.628* 00 x 0.038" Wall Alloy 600. Heat M5442. N111 Annealed + 1190F/18 hr)
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Tensile Tests Results of the 600*F tensile tests are given in Table 4. Tabulated are:
- 1. The yield strength and ultimate tensile strength of the desaged tubes and the undamaged tube based on the actual cross section area.
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- 4. CgcLg}ggg The results of 600*F burst and tensile tests of intentionally daseged Alloy 600 OTW tubing leads to the following conclusions: -
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- 5. ACIMMIDBENf3 i R. C. Ritschard, J. A. Menti J. V. Monter, and E. M. Detsey of the ARC Chemistry & Corrosion Section set up and conducted the tests.
Tensile tests were done by J. Rochus of the ARC Meta 11ery Section.
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R. H. Emanue son G. J. Thous /
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- 1. R. H. Emanuelson and G. J. Thous. " Collapse Tests en Intentionally Dasaged Alloy 600 0T56 Tubing". Alliance Research Center LR:76:2341-74:1. April 26,1976.
- 2. Metals Haneook, 8th Edition. Volume 10 Failure Analyses and Prevention. American Society for Metals. Metals Park. Ohio, 1975, p. 64.
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