ML20046B629
| ML20046B629 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 07/29/1993 |
| From: | Simpkin T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| TAC-M84422, TAC-M84423, NUDOCS 9308050282 | |
| Download: ML20046B629 (21) | |
Text
T Commonwealth Edison O
1400 Opus Place O'
Downers Grove, Illinois 60515 July 29, 1993 t
Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention: Document Control Desk
Subject:
Zion Power Station Unit 1&2 Reactor Vessel Upper Shelf' Energy Response to Request for Additional Information TAC Numbers M84422 and M84423 NPC Docket Nos. 50-295 and 50-304
References:
(a)
May ll, 1992 letter from D. Chrzanowski to Dr. T. Murley (b)
June 23, 1993 letter from C.
Shiraki to D.
Farrar
Dear Dr. Murley:
i With Reference a), Commonwealth Edison Company (CECO) submitted for NRC review and approval a report titled " Low Upper Shelf Toughness Fracture Analysis of Reactor Vessels of Zion Units 1 and 2 for Load Level A and B Conditions."
The purpose of the report is to demonstrate that margins of safety equivalent to those required by Appendix G of ASME Code Section III-exist for the Zion vessels.
A request for additional information was transmitted with Reference b), The purpose of this letter is to provide CECO's response to this Reference b) request.
Attached to this letter is the subject response.
Please contact his office with any questions.
7 Respectfully, M
T.W., Simpkin Nuclear Licensing Administrator TWS/gp cc:
C.
Shiraki - Project Manager - NRR J.D. Smith - Senior Resident Inspector I
B. Clayton - Region III A [-
$h 9300050282 930729 t o n a u t r -n r e:.wr t /s PDR ADOCK-05000295 ps P
PDR ind
]
~. - -
RESPONSES TO RAI ON BAW-2148P BAW-2148P " Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of Zio.7 Units 1 and 2 - for load level A & B conditions," March 1992.
p 1.
Repcrt BAW-2148P, Revision 1, indicates that the Atypical Weld is not the limiting weld for both Zion Units 1 and 2, and does not need to be addressed in this report. To firmly estabikh this point, provide the following information:
-t The Charpy curve and the analysis used in determining the USE of 79 ft-lb for the Atypical Weld listed in Table 2-2.
The hours of stress relief received by test specimens of the WF-70 and the Atypical Weld, and the hours of stress relief received by the corresponding vessel s
beltline welds.
A plot showing the comparison of J-R model curves for Weld WF-70 and the Atypical Weld, along with the experimental data. If some data for WF-209 i
specimens taken from Capsule CR-3 and tested in 1990 are pertinent to the Atypical Weld, then they should be supplied. If the Atypical Weld has any correspondence with the HSST 60 series welds, they should be identified.
Response
o A list of all Charpy energy data on the Atypical Weld is shown in the attached j
Table 7 from BAW-10144A. The 79 ft-lb Initial USE shown in Tables 2-1 arid 2-2 of BAW-2148, Rev.1 is the measured value at 260 and 300F.
I o
Str' Relief Time WF-70 Specimens 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (nozzle belt dropout)
Atypical Weld 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> l
RV Beltlines 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> (Zion 1) 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> (Zion 2)-
o a)
There is no compact fracture specimen test data available for the Atypical Weld to compare with the model. Only Charpy impact energy data and four K,c data were obtained. The K,c data are all bounded by the ASME K,c Curve.
b)
No WF 209 fracture toughness data from the CR-3 capsules are pertinent j
to the Atypical Weld.
I c)
To the best of our knowledge, no HSST 60 series welds are related to the i
Atypical Weld.
h: \\mnsdr taf \\tetmm2.wpf
,,,.,-7
..,v.
Table 7.
Pre-Irradiation Charpy Impact Data for Atypical Weld Metal Test Absorbed Lateral Shear Mach.
Specimen
- temp, energy, expans.,
- fracture, diag.,
No.
F ft-lb 10-3 in.
figure PPO47 0
21 20 20 12
,PP050 15 27 26 30 12 PP030 30 31 34 30 12 PPO42 40 34 32 30 12 PP023 55 30 30 30 12 PP027 75 36 36 40 12 PPO48 90 44 46 100 12 PPO40 105 46 45 100 12 PP009 120 56 63 100 12 PP012 135 39 42 100 12 PP013 150 63 72 100 12 PP025 200 68 69 100 12 PPO45 230 78 77 100 12 PP020 260 79 77 100 12 PP019 300 79 78 100 12 s
. Babcock & Wilcox
2.
The report indicates that a method other than that in Regulatory Guide 1.99, Revision 2 was used for calculating fluence at a quarter thickness from the fluence at the inside surface.
This method should be provided and its use justified.
Response
The plant specific attenuation curve was used to calculate the quarter thickness fluence from the inside surface fluence, based.on the atached Figure II.2-5 of WCAP-10962, Revision 2.
4 l
r 9
WESTINGHOUSE CLASS 3 1
FIGURE II.2-5 RELATIVE RADIAL DISTRIBUTION OF FAST NEUTRON (E>1.0 MeV) FLUX AND FLUENCE WITHIN THE PRESSURE VESSEL WALL ZION UNITS 1 AND 2 3...
t...
l Y. L: "._"; " _":_
==.
=
- 1
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~=
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s_
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e
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p ---y-g*
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. _ =
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3 1/2 T
=
'x
'4-l
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5 i].
.iA: }- 33 5siflI -;:fi-li. ~. li s. i r-- i' 3/4 T. :~_ '~ 7IJ._ ~E; s= 4. =_ _=. __m_ _;R =._ _- _nfEzi zzr=T7 E_1 l ._ =.. _ cr-. .__..t.. _ _ _ _ ~@ i 2. i 0 2 4 6 8 10 12 14 16 18 20 12 DEPTH INTO THE PRESSME YESSEL l 1 4414s/061490 10 38 i
3. A complete list of input parameters and conditions for the thermal i v2 21 ksi.in should be supplied. This includes analysis leading to K,i = conductivity, specific heat, therma density, the resulting value of thermal diffusivity, coefficient of thermal expansion, elastic modulus and Poisson's ratio (for both cladding and base metal); also the time history of the heat transfer coefficient and fluid temperature. Provide the corresponding K by using the currently proposed equation in Appendix X. n
Response
A list of input data is given in Table 1. These data are for the base metal. In an Appendix G analysis with a quarter thickness flaw, the cladding effect is ignored because it has little effect on a deep flaw. The KI thermal (KIT) of 21 ksifi5 was based on the results of the ASME Section XI round robin calculation reported in EPRI TR-100251, " White Paper on RV Integrity Requirements for Level A and B Conditions," January 1993. (See attached tables 4-1 and 4-2.) The round-robin calculation used a vessel thickness of 8.7 inches compared to Zion's thickness of 8.44 inches, which is conservative. The KIT equation currently in Code Case N-512 yields 22 ksiff5 using the RV thickness of 8.44 inches and a/t of 0.25. The new proposed equation for Appendix X equation using appropriate material properties (See attached committee correspondence from K. Yoon to S. Yukawa) produces 19.7 ksiff5 when the nessel thickness of 8.44 inches is used. This is believed to be the correct value for KI for a thermal gradient with a 100F/ hour cooldown. The film coefficient was selected as a constant over the entire cooldown, 1000 Btu /hr-F-ft. The fluid temperature time history is based on a constant 100F/ hour cooldown rate starting at 570F. r W 8
i Table 1 Input Material Properties The following is a list of temperature dependent material properties: TEMP E ALPA K CP RHO POISSONS RATIO 10., 29.989, 7., 286.6,.097, 491.7, .3 70., 29.899, 7., 278.4,.104, 490.9, .3 100., 29.828, 7.01, 275.1,.107, 490.5, .3 I 150., 29.681, 7.05, 270.8,.111, 489.9, .3 200., 29.503, 7.10, 267.6,.115, 489.2, .3 250., 29.301, 7.15, 265.3,.118, 488.6, .3 300., 29.082, 7.21, 263.7, .12, 487.9, .3 350., 28.847, 7.25, 262.5,.123, 487.3, .3 e 400., 28.597, 7.3, 261.6,,125, 486.7, .3 450., 28,331, 7.34, 260.6,.126, 486., .3 500., 28.048, 7.39, 259.5,.128, 485.4,.3 550., 27.74, 7.44, 257.8 .130, 484.7, .3 600., 27.403, 7.5., 255.6,.133, 484.1., .3 650., 27.026, 7.58, 252.5,.135, 483.4, .3 700., 26.599, 7.70, 248.4,.139, 482.8, .3 i where TEMP = temperature, F + 6 E = Young's modulus, 10 psi Alpha = thermal expansion coefficinet,10-6 in/in thermal conductivity, Btu /in-hr-F K = CP specific heat, ptu/lbm-F = Rho density,lbm/ft = TD thermal diffusivity = TD = K/(Rho x CP) l i I
ASME sanwo x! App dr c asemew 1htWe 41 semple Problem tor CMt. of Pressure 4mperatum Hestup and Cooldown Umits ,, compwe trw esses ireenemy factor 6, ese is prenewe imeding ensy ser a ven itse gpven ine esmewing informenon: veness and meer Geometry J s.7 inches = l vesses west Twennes. 0.2 h:hes = Qadeg Thtcamens 10 Vessel Mean Redlue to Thecknees Roso (M) = I 2.175 incnos = mas Depen (men) 1106 inches = New1.ength Aslai = Fisw Clytentarton SamhestaticM surface new = Flow Shape Note: Use matertes properttee from ASME Section is.1966 Ed. I ! Assume preneure = 2000 peJ. edicate if calculeuen ecludes pressure on the creca ' ace f 550*F to 100*F
- 2. Calcutete the strose intensity factore Ke due to undorm cooedown frorn an estial steady-stat heer trenefer coefncient of et coolewn reams of 50*F/hr and 100*Fh for a quarter-thscknees inside surface new. Assume al 1000 Stu/hr-ft**F.
h e*=n. (a) Ca6culate K, at oopth a=0 and a=2.175 oches se a function of time dunng t e rw d f time during tre erw**wn (b) Calculate the temperature at depth a =0 and a=2.175 inches as a func on o2175 cches.e reached dunng the (c) Ca6culate the times at whch the maxsmum value of K. at depth a =0 and a =. I 1 For an outsade surface ffaw having a depth of a quarter 4hscknees, ca6culate the :horm transient from 100*F fo 550*. lap Ca&culate K. at depth a =0 and a=2.175 oches as a function of time h tp 75 :nches a reached dunng the heatup. ic) Calculate me tunes at when the maxarnum value of K, at depth a =0 and a.2.1 l R pressure ves.sel. Assume tar to 1miting matenal *
- 4. Construct heatup and cocidown pressure. temperature Jmst curves for a PW i
m the best!!ne e an amal weld with the followmg propertfee. i umating veeses soluine weed untertes 0.16 wt % = Cu 0.57 wt % = NI 0*F Iruttal RTg = 56'F = Margen 1 x 108 vem2 (E > 1 ueV) t Fluence et ID Surface = Surface RTa = 200'F = 179'F RTc t 1/4t e = 139'F Ric t 3/4t a calculated using Regulatory Guce 1.99. Revtalon 2 with a chemetry factor of 144*F l Note: RT,cr F at a heerup rate of 50*F/hr. (a) Evaluate the allowable pressure vs. temperature timite durfng bestup from 100*F to $50* l
- F at ::coldown rates of 50'F/hr and (b) Evaluate the allowable pressure vs. temperature dunng coceown from 550'F to 100 100*F/hr.
0*F/hr). I (c) Evaluate allowable pressure vs. temperature for a steady-state condition (I o.. h d in calculating the allewable strnits, do rot induce add tional instrument arror margn, other than no reactor coolant system pressure and temperature. 4-15 b N I
.... = A t ASME Sectar D A;,. 'it G ?r ' i, lhble 4-2 :r---hi of &arpple Problem Resuits Working Greg Operating Plant Crfterie August 2s, tsee Pteesene K,(K,,),(kai in8) Anehois Prosaure ces Crack Fece N ^.._ try Yes No Appenes G 84W - M 1980 57.4 52.0 56.3 - M 1982 58.5 i CE 513 48.5 - (x - 2.175)
- 6. s l
-(x = 2.175) 57.0 51.2 80.1 -(surface) 38.5 34.8 ORNL 90.0 -(7Vt 10.5) Novetech 00.5 52.3 -(AZ. PVP 5/85) 55 8 W,, = 0.1) NUSCO 57 0 fofa, = 0.5) 50 0 55.8 Teiedyne 48.1 Thermal K, (K ) i Anefreie Xe (so*F/hr) Mn'*) K (100*F/hr)(kaMn'8) ! Performed try Hootup Cooldown Hestup Cooldowei B&W g 11.2 10 8 CE 21.0 f - t/4r i -11.3 11.3 l - 3/48 826 -826 22.8 SLA - 16.5 - a = 2.175 10.7 - surface 21.1 20.1 N<wtech - App X. 10.7 -Influence CoeM. 21 2 21.1 NUSCO 13.1 12.8 24.8 Tenedyne I -r 2.175 l - sur= face to 6 20.6 10.3 20.1 i e I s 4-16 b
s d I COMMITTEE CORRESPONDENCE ADDRESS WRITER CARE OF: COMMITTEE: Kenneth K. Yoon XI, WG-Flaw Evaluation D&W Nuclear Technologies Co. 3315 Old Forest Rd.
SUBJECT:
Lynchburg, VA 24506-0935 K Thermal Calculation (804) 385-3280 DATE: July 5,1993 TO: Copy to: Sumio Yukawa R. Cipolla J. Bloom J. Merkle D. Scarth
Dear Sumio:
In response to your letter dated Jn : 18,1993, I performed KIT calculation for all in Table I with a list of input parameters. three sets of materials. The results are - v It appears that the 302A&B has the high: ' < 1i values but not much. I also went ahead to scale back the equation to fit these values oest as shown in Figure 1. The new equation is now as shown below. I am glad that we performed the material sensitivity study. It appears that you covered all vessel materials. I hope that we can imp!ement this type of corrected equation to Appendix X if everyone comes up with a similar result. KIT = 0.001 (CR) t ^ 2.5 F3 mhere F3 = A0 + Al*(a/t) + A2*(a/t) ^ 2 + A3'(a/t) ^ 3 A0 = 0.617 A1 = 2.795 r A2 = -6.646 [ A3 = 3.157. Attachments:
TJe4 ~ v. Some PCRIT 5.0 Inputs Property Value R, 80.0" t 8.0" t .4 3/16" ei pi J00 psi z h 1000 Btu /ft hr F a 45.2 ksi v 2 p 485.0 lbm/ft Thermal Material Properties Material E a (TE) s (TC) 6 (TD) e, 10 psi 10-6 Btu /hr-Btu /l bm'- 6 2 2 in/in/'F ft.*F in / min ft /hr op 302-AaB 28.0 8.08 24.7 1.008 0.420 0.121 A533-B-1 26.7 8.08 23.8 0.979 0.408 0.120 508-2&3 26.7 7.77 23.9 0.974 0.406 0.12) 0.128 cladding same as base metal 10.0 PCRIT 5.0 Results: Maximum K,, Haterial Cooldown Rate Maximum K,, (ksi/in) at ) 1/40 t 5/40 t 10/40 t 302-A&B 50 4.2 7.7 8.6 100 8.5 15.5 17.2 A533-B-1 50 4.2 7.6 8.4 100 8.3 15.2 16.8 508-2&3 50 4.0, 7.3 8.1 1 100 8.0 14.7 16.3
4 T't cn 4-- STRESS INTENSITY FACTOR FOR THERMAL LOAD COOLDOWN RATES OF 100 AND 50 F/HR 30 - ~ EO FOR 100F/HR 25 - COMPUTER OUTPUT FOR 100 F/HR a ~ EQ FOR 50 F/HR j 20 - COMPUTER OUTPUT FOR 50 F/HR u; 55 .M 15 N i' M 10 n A-------------- k-5 A I I 0 0 0.05 0.1 0.15 0.2 0.25 0.3 a/t 4
COMMITTEE CORRESPONDENCE ASME BOILER AND Tl.4SSURE VESSEL CODE ADDRESS WRITER: COMMITTEE: XI, WG-Flaw Evaluation 4925 Valkyrie Drive Boulder, CO 80301 (303) 530-2969 June 18, 1993 TO: J. Bloom, R. Cipolla, J. Merkle, D. Scarth, K. Yoon FROM: S. Yukawa
SUBJECT:
Material Properties for K thermal Calculations This memo gives physical properties for stress and K calculations for several commonly used RPV steels in response to my assignment at the last WG meeting (4/6/93). A review of RPV shell materials listing in EPRI TR-100251, " White Paper on Reactor Vessel Integrity Requirements for Level A and B Conditions" indicates that the following grades have been used in vessels for existing plants: SA 302A (one plant) SA 302B SA 302B Modified (presumably all to Code Case 1339 which is essentially identical to SA 533, Gr. B, Class 1) SA 533, Gr. B, Class 1 SA 508, Class 2 SA 508, Class 3 The nominal compositions for these steels are: Grade _C__(max ) MD HQ Hi CI V
- 302A,
>2" .25 1.1 .5
- 302B,
>2" .25 1.3 .5 533-B-1 & 302B Mod. .25 1.3 .5 .55 508-2 .27 .75 .6 .75 .35 .05 max i 508-3 .25 1.35 .5 .7 .25 max.05 max Based on these nominal compositions, my selections of the material groups for thermal expansion (TE), thermal 1 i
_= l t conductivity (TC), thermal diffusivity (TD), and elastic modulus (E) values in the Code tables in Section II, Part D are: gy g II TC & TD E 302A Grp D Mn-1/2Mo Grp A 302B Grp D Pn-1/2Mo Grp A 533-B-1 Grp D Mn-1/2Mo-1/2Ni Grp B 508-2 Grp A 3/4Ni-1/2Mo-1/3Cr-V Grp B 508-3 Grp A 3/4Ni-1/2Mo-1/3Cr-V Grp B can be seen that 302A and 302B and 508-2 and 508-3 are in the It same grouping for all values. Also, it's evident that the Code is not consistent in using the same grouping designation among the various properties tabloa. Please let me know if you have routinely used other groupings in your calculations. In the meantime, I have used the above groupings for a list of values at 300 0F. In the case of TE values, the listing shows three values. The first is the mean coefficient for 70 to 300 OF and the second is the value for 70 to 550 0F. The third is a calculated value for cooldown from 550 to 300 CF obtained as the difference in the total expansion to 550 and to 300 CF divided by 550 minus 300 or 250'0F. I think this gives the mean coefficient for the cooldown case. The values for TC, TD, and E are the values at 300 OF. The units for the listed values are: TE = 10-6 (in/in/0F) TC = Btu /hr-ft OF TD = in2/ min E = 106 (psi) TE (mean) Grade to 300 0F to 550 0F 550 to 300 TC TQ E P 302A&B 7.43 7.77 8.08 24.7 1.008 28.0 A533-B-1 7.43 7.77 8.08 23.8 0.979 26.7 508-2&3 6.87 7.34 7.77 23.9 0.974 26.7 I believe the purpose of collecting these valuets was to determine how much effect they had on cooldown thermal K. For this purpose, I suggest using the 550 to 300 0F cooldown TE t values and the listed TC, TD, and E values. For ease in 2 b n
r.** \\ l i comparison, I suggest the following geometry and cooldown parameters: Vessel wall thk. 8 in. 10 R/t Cooldown rate 50 and 100 CF/hr Flaw location and depth ID, 1/8 and 1/4 t Flaw aspect ratio 1/6 Heat transfer coeff. 1000 Btu /hr-ft2 op This is a shortened list of the cases calculated by Ken Yoon in his April 22, 1993 memo. Cladding can be ignored although it 'c can be expected to have an influence on a shallow flaw. Sufficient stress values to compare through-wall stress distributions and K values at the two flaw depths chould be provided. I would be willing to collect and summarize the results if they are sent to me at least a week before the next WG meeting. Please let me know if I have forgotten anything or if there are any questions. pO C D P 3 ^ - - - - - - - - - - - -
4 I l 4. Table 4-2 of the report shows that 17 weld metals were included in the i data base used to develop the J-R correlation model. A corresponding l table, Table 4-2, in BAW-2118P shows 23 weld metals instead. It should be i confirmed that there is only one correlation model applicable to all B&W. Owners Group plants. l
Response
The Table 4-2 in BAW-2118P was revised by Florida Power and Light Company in a letter in response to RAI on BAW-2118P dated September 13, 1992. The revised table 4-2 in BAW-2118P is identical to that in BAW-2148P. + 5. The legends that appear in Figures 5-1 through 5-10 of the report are not readable, and clear replacement copies should be supplied. Reponse: Figures 5-1 through 5-10 are attached as requested. i s 1 l
i 4 Fioure 5-1 Soecimen PR303 Data with Jd Model 48 Curves Cu .35, B,-0.315, T - 390 F, pt - 8.45 Jd. tdph y 4 MO. DEL 48 rnman 33 uooct.a rn r>= w I _. 7 gg ,.. ' f as g4 i n2 -- - - - e Data beyond J contrd Irnt 4 10 R3 a1 22 a3 C4 C.5 C3 te. h Fiaure 5-2 Specimen PR304 Data with Jd Model 48 Curves Cu =.35, B,=0.315, T = 320 F, dt = 8.45 1.4 MODEL48 rnsan gy MODEL48 rnear>2t7 g ., / ---.._s- . _. _. - + g gg ~ g4 i - - - +
o Data beyond J contrd famit C.2 gg.-
C4 E1 C.2 C.3 C.4 C.5 C.3 A4. h 5-9 i 1
4 Ficure 5-3 Snecimen PR73 Data with Jd Model 48 Curves Cu .35, B,=0.749, T - 550 F, dt - 8.45 1 1._. ___uy__.__ j,4 i Wh0EL48 mean u i i 1 MooEL4em eva i i ~ l ~ 1.0 1
F---------
as i 4 - + - - - as ,/ ",/ gg +..-m.. ---.-4 - ~ - - - _. -. - + -. - .--v..-s t ]e Data beyond J control lima gy i gg CD E1 C2 0.3 24 0.5 0.8 am. h Fiaure 5-4 Specimen PR81 Data with Jd Model 48 Curves Cu =.35, B,=0.749, T = 480 F, dt = 8.45 c j,4 e Data beyond J congol lin.n jy .. __ j i + I { ~ jJ ._6_ i 5 I \\ i O.S t gg / f i PR61 L4 l* c MODEL48 rreni i () I gj L-MODEL48 memv20 l e a a C3 C1 02 0.8 8.4 c.5 C.S be. h 5-10 I l a
Ficure 5-5 Spec i PR100 Data with Jd Model 4R Curves Cu .35, 8,-0.4, T - 480 F, dt - 8.45 Jd,Mp.h l~ -~+ rm oa ~ ~-- ~ 1.4 m i .._....s..-- .w i mm, i 1.0 gg j i 3 g ..k - .---...-.-.-.-4--- I - -- ----
- Data beyond J e intrd Ema -
c2 l ? co to at a2 cm a4 c.s e.s i be, M 7 Fiaure 5-6 Specimen NN005T Data with Jd Model 48 Curves Cu .35, B,=0.8, T = 430 F. dt 0.0 gg , NN005T + - - - - - - - - - - - - - - - - - - - - + - - - - A0 MODEL48 rrman l WODEL4B rneart2 10 - + - - - - - - e t 2, .)x i. i i 1.o --L----"-. - ?- - f e Data beyond J controllimit OLC +' C3 0.1 0.2 CJ R4 0.5 0.8 As, M 5-11 a
Fiaure 5-7 Snecimen NNOI9 Data with Jd Model 48 Curves Cu .35, B,-0.4, T - 550 F, pt - 0.0
- ~
1.4 ~~~~ < y y f p*** '~ ~ ~ ~ ~ 1.0 -- l- - ~ ~ ' ~ ~ -~ - *- NN019 / O WoocL48m n--- ~ 0.8 / - ~ ~ ~ ~ ~ ~ ~ ~ ~~~ ' ~ ~ ~ ~ s 0.6 l MODEL48 maarv2a / fl - - - ~ ~ ~ ~ ~ ~ ~ ^ - ~ ~ ~ 0.4 f [ ~-
- Data W J ""tr ' 5"*
0.2 0.00.0 0.1 0.2 0.3 0.4 0.5 0.6 aa. in Fiaure 5-8 Specimen NN007 Data with Jd Model 48 Curves Cu =. 3 5, B,=0. 4, T = 480 F, dt = 7.5 gg 1.4 uncor . MO. DEL 40 rnsan 3y MODEL40 rnser>2a gg _._4_ Ed-R*&\\z. _ - __.__- _ . -n_ u u h.-___,w 4'A E as i gg _... _ -. e Data beyond J control htmt ( t f s C2 C1 C.2 C3 C,4 45 C.2 AA h 5-12
i l Fiaure 5-9 Soecimen NN006 Data with Jd Model 4B Curves Cu .35, B,=0.4, T - 550 F, 4t - 1.17 i 1,g = uooa<e m. n MODEL48 nwart2a 1.0 ~ / s ~.__ as /, 13 14 C.2 e Data beyond J control lima a ao EC C.1 22 12 14 c5 c.2 LA h Fiaure 5-10 Soecimen NN0ll Data with Jd Model 48 Curves Cu =.35, B,=0.4, T = 350 F, et = 0.0 ,sd. kip.in 1.4 _j'._..._...._.-..._ y' a - }.2 /. NNO11 1.0 L- ~~ wooa40 mean 0.8 u ca4em=2a _._i -. _ _. _ _ 0.6 O.4 ~~ -- O.2 o.o 0.0 01 0.2 0.3 0.4 0.5 0.6 oa,in 5-13 -}}