ML20062J404

Reactor Pressure Vessel Surveillance Program:Capsule Basket 2,Capsule Basket 3 & Neutron Dosimeter Monitor

ML20062J404
Person / Time
Site:	Dresden, Quad Cities
Issue date:	03/01/1975
From:	Denning R, Farmelo D, Perrin J COMMONWEALTH EDISON CO.
To:
Shared Package
ML17179B166	List: ML17179B165 ML20062J404 ML20062J407 ML20062J410
References
NUDOCS 9311040371
Download: ML20062J404 (100)

Text

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O FINAL REPORT k

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QUAD CITIES NUCLEAR PLANT UNIT NO.1 REACTOR PRESSURE VESSEL SURVEILLANCE PROGPJJi: CAPSULE BASKET NO. 2, CAPSULE EASKET NO. 3, AND NEUIRON DOSIMETER MONITOR to COMMONWEALTH EDISON COMPANY by J. S. Perrin, D. R. Farmelo, t

R. S. Denning, and L. M. Lowry i

March 1,1975 BATTELLE Columbus Laboratories 505 King Avenue Columbus, Ohio 43201 9311040371 931022 I

PDR ADOCK 05000237 P

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TABLE OF CONTENTS i

IAEC ii LIST OF FIGURES.

iii LIST OF TABLES............................

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1 7

SUMMARY

s 2

INTRODUCTION.,............................

4 CAPSULE RECOVERY AND DISASSEMBLY.....

10 SPECIMEN PREPARATION.............

12 EXPERIMENTAL PROCEDURES.

12 Neutron Dosimetry..........

14 f

Charpy Impact Properties.

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16 Hardness Properties.

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Tensile Properties.......................

1 19

-l RESULTS AND DISCUSSION.

19 Neutron Dosimetry.

26 Charpy Impact Properties....................

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Hardness Properties.

t 50 Tensile Properties...

57 CONCLUSIONS..

58 RtrExENCES.

APPENDIX A 1

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INSTRUMENTED CHARPY EXAMINAL ON...................

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LT ST OF TAT 4T FS

,k F OM SULE PASKET S LY 2

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TABLE 2.

INVENTORY OF-SPECIENS REMOVED FROM CHARPY AND TENSILE CAPSULES FROM CAPSULE BASKET ASSEMBLY NO. 3........

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'LJLE 3.

CALIBRATION DATA FDR THE BCL HOT IABORATORY CHARPY IMPACT MACHINE.

14 1

TABLE 4.

QUAD CITIES UNIT NO. 1 FAST NEUTRON DOSIMETRY RESULTS..

20 TABLE 5A. VALUES USED IN QUAD CITIES UNIT NO.1 DOSIMETRY CALCULATIONS.

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t TABLE 5B. ACTIVATION CROSS SECTIONS IN BARNS FOR QUAD CITIES UNIT NO. 1.........

21-TABLE 6.

CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO.1 IRRADIATED BASE ETAL FROM CAPSULE G1,.......

27

,t TABLE 7.

CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO. 1 IRRADIATED BASE METAL FROM CAPSULE G2.

27 TABLE 8.

CHARPY V-NOTCH IMPACT TEST RESULTS FAR QUAD CITIES UNIT NO. 1 IRRADIATED ESW WELD METAL FROM CAPSULE G1......

28 TABLE 9.

CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT l

NO 1 ESW WELD METAL FROM CAPSULE G2...

28 TABLE 10. CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO 1 ESW HAZ METAL FROM CAPSULE G1............

29 I

TABLE 11. CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO. 1 ESW HAZ METAL FROM CAPSULE G2............

29 TABLE 12. CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO. 1 SAW WELD METAL FROM CAPSULE G1............

30 TABLE 13. CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO. 1 SAW HAZ METAL FROM CAPSULE G1...

30 f

TABLE 14. CHARPY IMPACT PROPERTIES FOR QUAD CITIES UNIT No. 1....

41 TABLE 15. COMPARISON OF QUAD CITIES UNIT NO. 1 UNIRRADIATED AND IRRADIATED (CAPSULE G1) 50 ft-Ib TRANSITION TEMPERATURE 42 BEHAVIOR.

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LIST OF TAFTrs (Continued)

Page TABLE 16. HARDNESS PISULTS FOR QUAD CITIES UNIT NO.1 SPECIMENS..

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TABLE 17. COMPARISON OF UNIRRADIATED AND IRRADIATED AVERAGE HARDNESS RESULTS FOR QUAD CITIES UNIT NO. 1 SPECIMENS...

49

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TABLE 18. TENSILE PROPERTIES OF QUAD CITIES UNIT NO. 1 IRRADIATED SPECIMENS.

51 1IST OF FIGIMES I

FIGURE 1.

CAPSULE PASKET ASSEMBLY NO. 3(LEFT), CAPSULE BASKET ASSDBLY NO. 2 (RIGHT), AND NEUTRON DOSIMETER MONITOR ASSDBLY (TOP MIDDLE).....

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FIGURE 2.

TYPICAL CHARPY CAPSULE WITH CHARPY SPECIMEN.

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FIGUPI 3.

TYPICAL TENSILE CAPSULE WITH TENSILE SPECIMEN.

7 FIGUPI 4.

CHARPY V-NOTCH IMPACT SPECIMEN.

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i 11 FIGURE 5.

TENSILE SPECIMEN.....................

l FIGURE 6.

INSTRUMENTED CHARPY MACHINE.

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FIGUPI 7.

EXTENSOMETER EXTENSION ARMS AND STRAIN GAGE ASSEMBLY i

USED FOR TENSILE TESTING.

18 FIGURE 8.

CALCUIATED NEUTRON FLUX SPECTRUM AT 950 NEAR-WALL NEUTRON DOSIMETER MONITOR CAPSULE LOCATION (AFTER BRASHER AND 23 j

TDMONS)

FIGURE 9.

CALCULATED NEUTRON FLUX SPECTRUM AT 350 NEAR-WALL j

CAPSULE BASFIT ASSEMBLY LOCATION (AFTER BRASHER AND t

24 TIMMONS)..

1 FIGUPI 10. CALCULATED NEUTRON FLUX SPECTRUM AT NEAR CORE TOP GUIDE CAPSULE BASKET ASSEMBLY (AFTER BRASHER AND TIMMONS).

25 1

FIGURE 11. CHARPY IMPACT ENERGY VERSUS TEMPERATURE FOR QUAD CITIES UNIT NO.1 PASE METAL.

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l FIGUPI 12. CHARPY IMPACT ENERGY VERSUS TEMPERATUPI FOR QUAD CITIES l

UNIT NO 1 ESW WELD METAL.

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iv LTST OF FIGURPS (Continued)

Page FIGURE 13.

CHARPY IMPACT ENERGY VERSUS TEMPERATUPI FOR QUAD CITIES 33 UNIT NO. 1 ESW HAZ METAL,.

FIGURE 14.

CHARPY IMPACT ENERGY VERSUS TEMPERATURE FOR QUAD CITIES 34 UNIT NO. 1 SAW WELD METAL,

FIGUPI 15.

CHARPY IMPACT ENERGY VERSUS TEFFERATURE FOR QUAD CITIES 35 UNIT NO. 1 SAW HAZ METAL.................

I FIGURE 16, CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO.1 IRRADIATED BASE ETAL FROM CAPSULE Gl.....

36 CHARPY IMPA'CT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES FIGURE 17.

36 UNIT NO. 1 IRRADIATED BASE METAL FROM CAPSULE G2....

FIGURE 18.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 1 IRRADIATED ESW WELD METAL FROM CAPSULE Gl..

37 FIGURE 19.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 1 IRRADIATED ESW WELD METAL FROM CAPSULE G2,.

37 FIGURE 20.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 1 IRRADIATED ESW HAZ METAL FROM CAPSULE G1..

38 FIGURE 21.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 1 IRPADIATED ESW HAZ METAL FROM CAPSULE G2 38 l

CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES l

FIGUPI 22.

UNIT NO.1 IRPADIATED SAW WELD METAL FROM CAPSULE Gl...

39 FIGURE 23.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES 39 UNIT NO. 1 IRRADIATED SAW HAZ METAL FROM CAPSULE G1..

THE EFFECT OF IRRADIATION ON VARIOUS HEATS OF A302B/

FIGURE 24.

44 A533B-CLASS 1..

FIGURE 25a. COMPARISON OF 30 FT-LB TRANSITION TEMPERATUPI SHIFT VALUES FROM VARIOUS SURVEILLANCE PROGRAMS FOR SA302 GPdDE 45 B PRESSURE-VESSEL MATERIALS.

FIGUPI 25b. COMPARISON OF 50 FT-LB TPANSITION TEMPERATURE SHIFT VALUES FROM VARIOUS SURVEIL 1101CE PROGRAMS FOR SA302 46 GRADE B PPISSUPI VESSEL MATERIALS.

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v LIST OF FIGUDES (Continued) l Page FIGURE 26.

POSTTEST PHOTOGPAPHS OF QUAD CITIES UNIT NO. I IRRADIATED TENSILE SPECIMENS.

52 FIGURE 27.

POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 1 IRRADIATED TENSILE SPECIMENS..

53 FIGURE 28.

POSTIEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 1 IRRADIATED TENSILE SPECIMENS.

54 FIGURE 29.

POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 1 IRRADIATED TENSILE SPECIMENS...

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56 FIGURE 30.

TYPICAL STRESS-STRAIN CURVE.

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1 FINAL REPORT t

f on QUAD CITIES NUCLEAR PLANT UNIT NO.1 f

REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM:

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CAPSULE BASKET NO 2, CAPSULE BASKET No. 3, AND NEUTRON DOSIMETER MONITOR i

to i

COMMONWEALTH EDISON COMPANY i

from k

I BATTELLE l

Columbus Laboratories by

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i J. S. Perrin, D. R. Farmelo, i

R. S. Denning, and L. M. Lowry March 1,1975

SUMMARY

-i The radiation-induced ' changes in the mechanical properties of

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specimens removed from the Quad Cities Nuclear Unit No. I reactor were de termined. Materials evaluated include base, submerged-arc-weld weld metal, submerged-arc-weld heat-affected-zone metal, electro-slag-weld weld metal, and electro-slag-weld heat-af fected-zone metal.

l Charpy-impact specimens were used to determine changes in the i

traasition temperatures and upper shelf energies. The measured increases in transition temperature for the five materials are compared to changes observed for comparable pressure vessel materials irradiated in o_ther surveil-I lance programs. The trend band curve compiled with this data can be used to predict future shifts in the transition temperatures of the pressure vessel l

t because the capsules are irradiated at rates which lead the pressure vessel.

j All five materials exhibited appreciable drops in upper shelf energies.

The tensile specimen evaluation showed that the yield and ultimate strengths l

increased.

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t INTRODUCTION 1rradiation of materials such as the pressure vessel steels used in reactors causes changes in the mechanical properties, including tensile, impact, and fracture toughness.

These effects have been well documented in j

the technical literature.(1-7) Tensile properties show a decrease of both j

i uniform elongation and reduction in area accompanied by an increase in j

yield strength and ultimate tensile strength with increasing neutron l

exposure.

The impact properties as determined by the Charpy V-notch i

i impact test show a substantial increase in the ductile to brittle transition temperature and a drop in the upper shelf energy.

Commercial nuclear power reactors are put into operation with reactor pressure vessel surveillance programs. The purpose of the surveil-l lance program associated with a reactor is to monitor the changes in mechanica1' properties as a function of neutron exposure. The surveillance program includes a determination of both the preirradiation base line i

mechanical properties and periodic determinations of the irradiated mechanical properties. The materials included in a surveillance program are base metal, weld metal, and heat-affected-zone (HAZ) metal from the actual components used in fabricating the vessel.

The irradiated mechanical properties are determined periodically by testing specimens f rom surveillance capsules.

These capsules typically l

contain neutron flux monitors, Charpy impact specimens, and ten'sile specimens.

Capsules are located between the inner wall of the pressure vessel and the l

reactor core, so the specimens receive an accelerated neutron exposure.

Capsules are periodically removed, and sent to a hot laboratory for disassembly j

and specimen evaluation.

l Quad Cities Unit No.1 and Unit No. 2 both have surveillance programs.

These are describec in a report issued by General Electric ( ), and are based on ASTM E185 " Surveillance Tests on Structural Materials in Nuclear Reactors".(

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At the time of initial operation of these two reactors, the pressure-i temperature operating curves were based on the 30 f t-lb transition tempera-ii ture of the limiting materials. During the life of the reactor, the I

operating curves are to be revised to account for the increases in the f

transition temperatures of the vessel materials. Both the 30 f t-lb and 50 f t-lb transition temperatures are presented in the present report.

l A previous report covers the preirradiation base-line tensile and Charpy impact properties of five materials from the reactor.(10)

These i

materials include base metal, submerged-arc-weld (SAW) weld metal, SAW HAZ metal, electro-slag-weld (ESW) weld metal, and ESW HAZ metal. The present report describes the results obtained from examination of two capsule basket assemblies and a neutron dosimeter monitor assembly removed from the reactor.

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In addition to the nomal infomat' ion obtained during a Charpy

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impact test, additional infomation was determined using an instrumented

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Charpy impact machine. The additional infomation is reported in Appendix A of this report.

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CAPSULE RECOVERY AND DISASSDiBLY The transfer of the two capsule basket assemblies and the neutron dosimeter monitor assembly from the vessel to the spent fuel pool was handled by reactor personnel. After transfer, they then sectioned the assemblies in the spent fuel pool using an H. K. Porter hydraulic cutting tool. After arrival of the shipping cask and BCL personnel, the cask was put into position adjacent to the pool with the cask lid removed. The i

4 three assemblies were individually loaded into the cask. This consisted of i

hooking onto the samples with a pipe and hand transferring them from the j

pool into the cask.

The cask lid was installed, bolted in place, and the exterior surface of the cask was decontaminated by reactor personnel. After f

decontamination, the cask surface was below the maximum allowable shipping 2

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limits of 2200 disintegrations /100 cm / min SY and 220/ disintegrations /100 cm /

min c.

The cask was then shipped to the BCL hot laboratory facility by commercial carrier.

Upon arrival at BCL, the three assemblies were removed from the I

cask and transferred to a hot cell for visual examination and disassembly.

Figure 1 shows Capsule Basket No. 2, Capsule Basket No. 3, and the neutron f

i dosimeter moni1or assembly. Visual examination revealed no unusual features j

or damage, wit's the exception of a slightly bent hanger attached to Capsule

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Basket Assembly No. 2.

Capsule Basket Assembly No. 2 had the identification j

"117C3729G-1". Capsule Basket Assembly No. 3 had the identification "117C3 729G-2".

The monitor assembly had the serial number identification t

"6509451".

The two capsule basket assemblies were cut apart using a flexible f

abrasive wheel attached to a Mototool. Capsule basket assembly Np. 2

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contained four Charpy capsules and five tensile capsules. The identification numbers of these nine capsules were as follows, with the first being located closest to the identification number end and the last being located furthest f

from the identification number end of the capsule basket assembly.

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FIGURE 1.

CAPSULE BASKET ASSEMBLY NO. 3(LEFT),

l CAPSULE BASKET ASSEMBLY NO. 2 (RIGHT),

AND NEUTRON DOSIMETER MONIIOR ASSEMBLY l

(TOP MIDDLE) i l

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Tensile capsule G2 Tensile capsule G1 Tensile capsule G3 Charpy capsule 117C3570G1 Tensile capsule G4 Tensile capsule G5

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Charpy capsule 117C3570G2 l

Charpy capsule 117C3570G3

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Charpy capsule 117C3570G4 Each Charpy capsule contained an iron, a nickel, and a copper dosimeter wire.

Capsule basket assembly No. 3 contained two Charpy capsules and three tensile capsules. The identification numbers of these five capsules were as follows, with the first being located closest to the capsule basket' assembly end with the identification number, and the last being located furthest from the identification number end, i

t Tensile capsule G1 i

Tensile capsule G3 Tensile capsule G5 Charpy capsule 117C3570G1 Charpy capsule 117C3570G2 I

Each of the two Charpy capsules contained an iron, a nickel ' and a copper

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dosimeter wire.

5 A photograph of a typical Charpy capsule shown with a single Charpy impact specimen is presented in Figure 2.

Figure 3 shows.a typical-l tensile capsule with a single tensile specimen. Charpy capsules contain up j

to 12 specimens per capsule. Tensile capsules contain two specimens per capsule.

'l Charpy and tensile capsules were cut apart using the same technique-and equipment as used for the capsule basket assemblics. An inventory of specimens is listed in Table 1 for capsule basket assembly No. 2 and in Table 2 for capsule basket assembly No. 3.I")

(a) In Inter sections of this report capsule basket' assembly No. 2 and capsule basket assembly No. 3 are referred to as " capsule G1" and

" capsule G2", respectively.

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FIGURE 2.

TYPICAL CHARFY CAPSULE WITH CHARPY SPECIMEN l

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FIGURE 3.

TYPICAL TENSILE CAPSULE WITH TENSILE SPIIIMEN I

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- i TABLE 1.

INVENTORY OF SPECIMDIS RD10VED FROM CHARPY AhT i

TDiSILE CAPSULES FRG1 CAPSULE BASKET ASSEMBLY NO. 2 i

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C" harpy Capsule G1 c2 G3 G4 M3D MAM P36 P63 M4M MDB P15 PAB t

M5Y MA6 P3T PAM M57 M7K P2Y P6Y M3E MLD P3K M4K MLA P22 i

M4U ML4 P4K M4L MKE P1K i

M7Y

.MK4 P7A M7U MKT P7B 1

M7M MPE

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MD7 MLK P7Y

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Tensile Capsule' t

ci c2 c3 c4-c5 PD6 PPB PJ3 PUS.

PL6 PDM PPJ PJ6 PUM PLD l

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TABLE 2.

INVENTORY OF SPECDIENS RD10VED FROM CHARPY AND TENSILE CAPSULES FROM CAPSULE BASKET ASSDiBLY NO. 3 I

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Charpy Capsule G1 G2 l

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M24 1215 M3B MK5

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M22 1D17 M36 1216 l

MB2 MC5 1

MC6 MCL l

MC7 MCU MAC MCJ

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Tensile Capsule j

G1 G3 G5 PDT PJU PLB PDD PJD PLK (a) Specimen identification obliterated during removal from capsule; identification

.j of PJU was inferred from inventory list supplied by Cor.nonwealth Edison.

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l SPECIMEN PREPARATION.

l The base material of the reactor pressure vessel is SA-302 Grade B.

Mechanical property specimens were prepared from actual vessel plate in accordance with GE specifications.( ) All specimens were made-from flat j

slabs taken parallel to the plate surfaces and at the 1/4 plate thickness.

l Base metal Charpy and tensile specimens were-machined with their longi-l tudinal axes parallel to the plate rolling direction. Charpy specLmen j

notches were cut perpendicular to the plate surfaces.

i The weld HAZ Charpy specimens were machined with the longitudinal l

axis transverse to the weld length and parallel to the plate surface. The axis of the notch is perpendici<'. to the plate surface. The notch radius is at the intersection of the base metal and the weld metal, f

The Charpy impact specimen design is shown in. Figure 4 It_is the i

i standard specimen design reco= mended in ASTH Standard E23-72. The tensile

!-t specimen design is shown in Figure 5.

It has a nominal 0.250 in, gage l

diameter and a nominal 1.00 in. gage length.

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FIGURE 4 CRARPY V-NOICH IMPACT SPECDiEN 4375-14 UNC ~2A 4

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L/GHT PR!CK PUNCf!

BOTH ENDS GAGE LENGTH / GAGE MARKS 2D6

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2 PL ACES 2 MACES 2DE 02 493

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/. Dr.2SO O!A. AT CENTER OF REQUCEO. SECTION. D's ACTUAL O DIA +.002 I

TO.005 ATENDS OF REDUCEO SECTION TAPERING TO D AT CENTER 2.GRINO REOUCEO SECTION 8 RAOl/ TO,2/RAOl/ TO BE TANGENT TO REDUCEO SECTION WITH NO CIRCULAR TOOL MARKS AT POINT OF TANGENCY OR WITHIN REDUCEO SECTIOt/. POINTOF tat /GENCY SHALL NOTLIE WITHIN REOUCEO SECTION.

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TENSILE SPECIMEN I

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i 12 JIPERIMENTAL PROCEDURES This section describes the procedures used in the determination i

i of neutron exposure and the impact, hardness, and tensile properties. All l

testing and' evaluations were performed at Batte11e's Columbus Laboratories.

Original data is recorded in BCL Laboratory Record Books 31223, 31230, and

31681, i

Neu* tron Dosimetry Neutron dosimeter wires were located in the neutron dosimeter monitor capsule and in each of the two capsule basket assemblies. The I

neutron dosimeter monitor capsule contained three iron and three copper wires.

Each Charpy capsule in the two capsule basket assemblies contained f

one iron, one copper, and one Ni-Co wire. The reactions and the associated ASTM standards are as fo110ws:(11,12,13)

Material Reac tion ASTH Standard Fe(n,p)54 Iron Mn E263-70 58Ni(n,p)58

. Nickel Co E264 Copper Cu(n,n)60Co E523-74

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l After removal from their containers, the wires were identified, pinced into individual vials, and transferred to the radiochemistry laboratory. They were then cleaned by wiping using successive swabs containing dilute nitric acid, distilled water and reagent acetone until residual contamination was j

completely removed. Weights were obtained to 0.0001 g on a calibrated

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analytical balance. The wires were then mounted for counting by gamma ray spec trometry.

The activation products were analyzed by gamma ray spectrometry using a 3 in. diameter x 3 in. long NaI(TI) scintillation crystal detector and a 400 channel analyzer capable of 7.0 percent resolution FVD. (full width half maximum) at the 0.662 MeV Cs-

"Ba gamma ray energy itsel.

m-13 The analyzer was calibrated-with standard reference materials obtained from the National Bureau of Standards. To calculate neutron flux from l

r' the dosimeter gamma activities at time of removal from the reactor, a knowledge of the reactor history and exact location of the samples was required as shown in the following equation-A I = Noc[1 - exp(-At )] or where

= ygg,,,,z ))

i c =* neutron flux in n/cm -sec I = disintegrations per second per gram at time of removal from reactor i

N = number of atoms of target isotope per gram of dosimeter c=effectivecrosgsectionatthesample location in em t = time in the reactor (equivalent full i

g power seconds)

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A = isotope decay constant, sec 2

The total neutron fluence is then equal to Otg.in n/cm.

The exact capsule location is necessary in that the effective I

cross section varies as a function of the neutron spectrum. ANISN,,a one dimensional transport code, was used to calculate the neutron spectrum at the capsule.

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h Charpy Impact Properties f

The impact tests were performed on a standard Wiedemann-Baldwin-I impact machine in accordance with the recommendations of the pertinent ASTM standard (14)

The accuracy of the machine was verified within a j

t 6-month period prior to use with standards purchased from the U.S. Army Materials and Mechanics Research Agency. The results are given in Table 3.

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I TABLE 3.

CALIBRATION DATA FOR THE BCL EDT LABORATORY CHARPY IMPACT MACHINE l

Average Standarp8 l

BCL Energy,

Energy, Variation l

Group it-lb ft-lb Actual Allowed j

l Low Energy.

12.4 12.5

-0.1 ft-lb 1.0 ft-lb Medium Energy 41.5 43.2

-3.97.

5.0%

High Energy 71.2 71.1

+0.1%

5.0%

(a) Established by U.S. Army Materials and Mechanics Researc,h Center.

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4 The impact machine is shown in Figure 6.

The Velocometer and

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Dynamic Response Module associated with the instrumented Charpy testing are l

I mounted on top of the impact machine. The oscilloscope located to the right i

1 of the machine is useC to record load-time traces during impact tests.

1 ASTM procedures for specimen temperature control were utilized.

The low temperature bath consisted of agitated methyl alcohol cooled with additions of I'iquid nitrogen. The container was a Dewar flask which contained a grid to keep the specimens at least 1 in, from the bottom. The height of i

the bath was enough to keep a minimum of 1 in, of liquid over the specimens.

The Charpy specimens were held at temperature for a minimum of least the i

ASTM recommended time.

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FIGURE 6.

INSTRUMDITED CHARPY PACHINE Velocometer and Dynamic Response Module are I

shown mounted on top of the Charpy impact

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machine.

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The tests above room temperature were conducted in a similar manner except that a metal container with a liquid bath was used. The bath used for temperatures from 70 to 212 F was water, and the bath used for temperature above 212 F was oil. The baths were heated to temperature using a hot plate.

The specimens were manually transferred from the temperature bath to the anvil of the impact machine by means of tongs that had also been brought to temperature in the bath. The specimens were removed from the bath and impacted in less than 5 sec.

The energy required to break the specimens were recorded and plotted as a function of test temperature as the testing proceeded.

Lateral expansion was determined from measurements made with a lateral expansion gage. Fracture appearance was estimated from observation of the fracture surface, and comparing the appearance of the specimen to an ASDI f racture appearance chart. ( }

Mardness Pronerties

'I Hardness tests were done using a Wilson Rockwell hardness testing machine.

Before testing, the hardness machine values were checked against two standardized test blocks having hardness values near the range of values expected for the test specimens. Five impressions were made in each of the standardized test blocks. The average of these values were within *2 hardness numbers of the standard values of the test blocks.

All hardness readings on specimens were taken using the Rockwell B scale. Specimens were Charpy impact specimens. Hardness readings were made on the Charpy specimen surface opposite the notched surface. Five readings were made in the general region halfway between the specimen notch and one end of the specimen. The minor load was first applied to seat the Rockwell B ball penetrator on the~ specimen surface. The major load was then applied, and the resultant dial hardness readings recorded.

l i

17 l

Af ter hardness readings were completed on the Charpy impact specimens, the hardness machine was again checked using the same two standardized test blocks. Five impressions were made in each of the two blocks. The average of these values were within *2 hardness numbers of the standard values of the test blocks.

i l

Tensile Properties The tensile tests we're conducted on a screw-driven Instron testing machine having a 20,000 lb capacity. A crosshead speed of 0.05 in.

per min was used. The deformation of the specimen was measured using a strain gage extensometer. The strain gage unit senses the differential movement of two extensonete,r extension arms attached to the specimen gage 1ength 1 in, apart. The extension arms are required for thermal protection of the strain gage unit during the elevated temperature tests. Figure 7 shows the extensometer extension arms and strain gage assembly used for

[

tensile testing. The strain gage unit is shown at the bottom of the figure next to the region of the extensometer arms where the unit is attached during testing. The extensometer was calibrated before testing using an Instron high-magnification drum-type extensometer calibrator.

i The irradiated tensile specbmens were tested at room temperature and 550 F.

Elevated temperature tensile tests were conducted using a three-i zone split furnace. The specimens were held at temperature before testing to stabilize the temperature. Temperature was monitored using a Chromel-Alumel thermocouple in direct contact with the gage section of the specimen.

Temperature was controlled within *5 F.

The load-extension data were recorded on the testing machine strip chart. The yield strength, ultimate tensile strength, uniform clongation, r

and total elongation were determined from these charts. The reduction in area was determined from specimen measurements made using a vernier caliper, i

+

5 9

I s

4 18 l

l t

d l

f j

l l

n I

i I

l l

M

• a*s 79 4 Y

.- mig 1

I

{

l

/

4 i

P4973 I

FIGURE 7.

EXTENSOMETER EKTDiSION ARMS AND STRAIN GAGE ASSDiBLY USED FOR TDiSILE TESTING i

a l

I f

~

l i

i l

19 RESULTS AND DISCUSSION Neutron Dosimetry Dosimeter wires from the neutron dosimeter monitor capsule and the two capsule basket assemblies were recovered and analyzed as described l

in the experimental procedures. A total of 18 iron and copper wires were f

gamma counted: three of each from the dosimetry monitor capsule, two of I

each from the wall region capsule basket assembly, and four of each from the top core region capsule basket assembly. Results of the counting are given in Table 4 in terms of fluence greater than 1 MeV and greater than 0.1 MeV.

An average total integrated fast fluence greater than 1 MeV from I

16 the iron dosimeters from the neutron dosimeter monitor capsule of 0.81x 10 9

i n/cm' was obtained. Good agreement was obtained from the copper dosimeters at i.02 x 10 n/cm.. Generally, the iron value is considered more reliable

[

due to its better known nuclear properties such as cross section-neutron energy relationship and threshold energy. The iron dosimeters from the capsule basket assembly from the wall region showed a slightly higher 16 2

i average flaence (>l MeV) of 1.03 x 10 n/cm. The top core area showed a j

large variation within the individual Charpy capsules. The~ measured iron 9

2 fluence greater than >l MeV ranged from 4.78 x 10 n/cm to 1.19 x 10 n/cm,

{

with an average value of 8.20 x 10 n/cm. Several factors enter into the calculations such as the reactor power history, neutron energy spectrum at the

{

particular location, and effective cross section for each reaction as a function of the neutron spectrum. Constants used for the two reactions are l

summarized in Table SA.

The saturation factor was calculated from

-A[j

-A fT-t )

N g

3 I

T (1-e

)e S

=

i j

pg where S = saturation correction factor g

F = fraction of full power

[

T = length of time interval T = total irradiation time

TAELE 4 Q"AD CITIES ITNIT No.1 FAST NEUTRON DOSIMETRY RESUt,TS TI,UX RATE 0. n/en -see FLUENCE Ot.(1,2),j 2 S s ple-Fe Cu Fe Cu 5e.

Copsule

> 1 MeV

>0.1 McV

> 1 MeV

>0.1 MeV

> 1 McV

> 0.1;tev

> 1 >;cy

>c.1 3:eV 8

8 0

16 16 16 16 1

Doct eter Ccpsule 2.39x10 3.83x10 2.63x10 4.19x10 0.932x10 1.49x10 1.02x10 1.63x10 8

8 8

16 16 6

16 2

Dosincter Capsule 2.38x10 3.79x10 2.67x10 4.2 5x10 0.925x10 1.48x10 1.04x10 1.65x10 8

0 0

IO 3

Oestecter Cepsule 2.05x10 3.26x10 2.59x10.

4.13x10 0.796x10 1.27x10 1 >10 1.61x10 8

I I0 16 16 Avg. 2.2 7x10 3.62x10 2.63x10 4.19x10 0.881x10 1.41x10 1.02x16 1.63x10 8

0 16 I0 1

Vall Capsule Dssket 2.62x10 3.uSx10' 3.18x10 4.70x10 1.02x10 1.51x10 1.23 x10 1.53x10 2

Vall Cepsule Basket 2.65x10f

_3.93x10 3.17x10 4.70x10 M310$

M3x10 1.23v10 1.53x10 8

8 6

I 8

~

0 6

10 16 16 Avg. 2.64x10 3.91x10 3.18x10 4.70x10 1.03x10 1.52x10 1.23x10 1.83r.10 o

1 Cere cepsule Basket 3.05x10 4.99x10 3.66x10 5.96x10 11.9x10f8 19.4x10 14.2x10 23.2x10 1I 11 1I 8

3 l1 11 18 18 0

18 2

Core Cepsule Besket 2.29x10k1 3.73x10 2.84r.10 4.60x10 8.91x10 14.5x10 11.0x10 17.9x10 lI II 11 18 18 3

Core Cepsuls Basket 1.85x10 3.01x10 2.30x10 3.75x10 7.20x10 11.7x10 8.95x10 14.6x10 I

0 II 18 7.79x10 _8 6.69x10.8

_10.9x10 4

Core Capsule Basket.

1.23x10 2.00x10N 1.72x10 2.80x10

_4.78x10 l1 1

0 8

l8 18 Avg. 2.11x10 3.42x10 2.52x10 4.29x10 8.20x10 13.3x10 10.2x10 16.7x10 (1) Epivaler.t full pcver days of operation was calculated to be 450 days.

(8) Date ef espsule removel frem the recetor was 4/1/74 r

m m...,

m,-,

1 21 l

TABLE SA.

VALUES USED IN QUAD CITIES UNIT NO. 1 i

DOSIMETRY CALCULATIONS eme. -

Target Threshold Product Isotope 7.

Energy Half-Saturation Reaction Target Abundance MeV Life.

Factor i

O Cu(n,ti)60Co 1007. Cu 69.17 5.0 5.26y 0.1452 54,

54 7

Mn 1007. Fe

-5.82 1.5 314d 0.5395 I

i t

s TABLE SB.

ACTIVATION CROSS SECTIONS IN BARNS FOR QUAD CITIES UNIT NO. 1 Fe Cu Capsule Locction

>l MeV

>0.1 MeV

>l MeV

>0.1 MeV -

Capsule Basket Near core top 0.143 0.0878 0.00113 0.000693 Assembly guide 90' Capsule Basket Wall-35' O.236 0.159 0.00420 0.00283 Assembly Dosimeter Wall-95*

0.225 0.141 0.00420 0.00264 Capsule b

.t i

22 th time Rat end of j interval t

t =

j N = number of time intervals A = decay constant i

For Quad Cities Unit No. I the average power was calculated to be 0.616 times the 2511 MW(t) full power rating.(16)

It should be mentioned that use of an aver' age power level rather than the detailed 1

power history in the above equation would have introduced errors of 10 percent and 2 percent in the case of Fe and Cu reactions, respectively.

_j Calculated fast neutron cross sections for the two reactions at three locations and over two energy ranges are presented in Table 5B.

To calculate the effective cross section, it was necessary to know the neutron j

spectrum at the capsule location where the neutron energies would be at a significantly higher range than the spectrum at the core edge. Figures 8, 9, and 10 are plots of neutron flux as a function of neutron energy at the three locations.( }

These were calculated by using the one dimensional transport code, ANISN. The effective cross section 3,7 g,y is calculated from the equation l

J=c(E)c(E)dE E= 0

1. >l MeV

~

=

c(E)dE E>l MeV i

where a and c are calculated over 27 energy groups.

F i

5 I

l l

QURD-CITIES 142 2511 BW B-MONITOR

]Q

- I 111111il l lilHlij l 111111)l 11111111l 1 1111111l 11111111l 1 1111111l 11111111l 11111111l 11111111l 1 illis

,e

~

~

Id

~

'~

y y

~'

F--

g g

_J tu C

Z' 2

0 10 c

p_.

U 2

2, to Z

i

-o 10 i v iimi i r itim

~ i i n tim i i riim i siiim i i riim i i ntim i i iiim i i rrim i r itim i iiiim

.10

10-

-10-

~10" 10" 10' 10

10*

1.0' 10 10' 1(f

~

~

NEUTRON ENERGY (MEV1 FIGURE 8.

CALCULATED NEUTRON FLUX SPECTRUM AT 95* NEUTRON DOSIMETER MONITOR CAPSULE LOCATION (AFTHL BRASilER AND TD&l0NS).

.n

.n.

.,.~,, - -, -.,

a,

.n

QURO-CITIES 142 2511 BWR NERB WALL (35,215) 10

._ i i n nui i s iiuti i s iini!

i i iinii isinniliituiolisiina i iinuij i s inin i iiine i sin x

o 10" I

w Q

~

r

_a uJ i

c E

-2 o

10 -

c r

a w

~

z 10, t iliiiri r iiritti i iiiiiri i i iritti r ilitrit r iittirt i n itiirt i iiiiirt i r ritiri t i rriirt i ritiir:

10*

10' 10

10

10

10"

~10 "

10*

10

10" 10' 10' NEUTBON ENERGY (MEV1 FIGURE 9.

CALCULATED NEUIRON FLUX SPECTRUM AT 35' NEAR-WALL CAPSULE BASKET ASSDiBLY LOCATION (AFTER BRASHER AND TIMMONS)'

dURD-CITIES 162 2511 BWR NEAR CORE TOP GUIDE.

10

-ii11:111liillinj i iiilliij i iiiiiiij i iiiiiiij i iiilliij i i siiiiij i iiiiiiij i i iiiiiij i i sitii:l i i siig X

D

_I 1 0

w 2

r e

CC L

._I LL.!

C 2"

2 o 10 e

l--

D 2

~]

W

~

~

-3 10 i iinm itinm i niinn iiinm i tinm i i nnm i i nnn i innml i innnil i einrel i i nrm 10*

10" 10' 10" 10*

10*

10*

10*

L10 '

10" 10' 10*

~

~

~

NEUTRON ENERGY (MEV1 FIGURE 10. CALCULATED NEUTRON FLUX SPECTRUM. AT NEAR CORE TOP GUIDE CAPSULE BASKET ASSDiBLY (AFTER BRASHER AND TD2 IONS).

P i

t 26 i

Charpy Impact Properties i

+

This section contains results and discussion pertaining to the Charpy impact testing. Appendix A contains further results and discussion relating to the instrumented procedures used during the impact testing.

The impact properties determined as a function of temperature are l

listed in Tables 6 through 13.

In addition to the impact energy values, the tables also list the measured values of lateral expansion and the estLmated fracture appearance for each specimen. The lateral expansion is a measure of the defonmation produced by the striking edge of the impact machine hammer when it impacts the specimen; it is the change in specimen thickness of the section directly adjacent to the notch location.

The frac.ture appearance is a visual estimate of the amount of shear or ductile type of fracture appearing on the specimen fracture surface, i

'The impact data are graphically shown in Figures 11 through 15.

5 These figures show the change in impact properties as a function of tempera-

[

t ture. Of particular interest is the temperature corresponding to the impact l

4 energies of 30 and 50 f t-lbs.

The energy level of the upper shelf is also i

of interest.

If the upper shelf energy is relatively low (e.g., 50 ft-lb or lower), the possibility of failure by low energy ductile tearing is greater.

In terms of fracture mechanics, a lower upper shelf is accompanied by low values of K the plane strain fracture toughness.

Ic, Figures 16 through 23 show the fracture surf aces of the Charpy i

specimens. Figure 16, as an example, shows how the fract'ure surface changes as the test temperature is increased for base metal specimens. The -20 F i

specimen (M4L) shows an almost flat fracture surf ace, with only 5% shear fracture appearance. This specimen absorbed only 15.5 ft-lb of energy during the impact test, a typically low value for the low temperature, brittle f

region of the Charpy curve. As can be seen in the figures, the amount of j

lateral expansion is quite small, and was measured as being only 11.5 mils.

i i

t

27

~

TABLE 6 CHARPY V-NOICH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO.1 IRRADIATED BASE METAL FROM CAPSULE G1 Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, Specimen F

ft-lb mils Percent Shear M4L

-20 15.5 11.5 5

M4U 30 21.0-17.5 15 R4K 55 27.0 21.0 20 M4M 80 25.0 24.0 15 M5Y 115 32.0 32.5 25 i

M57 145 55.5 50.0 40

(

M3E 212 88.0 73.0 100

[

M3D 300 81.5 67.5 100

{

E i

i TABLE 7.

CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO. 1 IRRADIATED BASE METAL FRCH CAPSULE G2 i

..i Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, 3

Specimen F

ft-lb mils Percent Shcar M36

-100 9.5 8.5 0

i M3B

-60 26.0 20.0 15 M4B

-20 38.5 34.0-20 MSL 30 55.5 50.0 30 M4E 55 75.0 64.0 75 M24 80 80.0 59.5 80 M22 145 108.5 7V.0 100 i

MSP 212 110.5 80.0 100 f

q c

k I

f 1

28 I

TABLE 8.

CHARPY V-NOKH IMPACT TEST RESULTS FOR QUAD CITIES

'l UNIT NO.1 IRRADIATED ESW WELD METAL FROM CAPSULE G1 i

l Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, Specimen F

ft-lb mils Percent Shear I

M7U

-20 4.0 5.0 0

MDB 30 12.0 15.0 5

M7K 55 4.0 7.5 5

MAM 80 26.0 22.0 10 M7M 115 45.0 35.0 35 M7Y 145 51.5 46.0 45 i

MA6 212 66.5 63.0 70 i

MD7 300 89.0 76.0 100

'i TABLE 9.

CHARPY V-NOICH IMPACT TEST RESULTS FOR QUAD CITIES 3

UNIT NO.1 ESW WELD METAL FROM CAPSULE G2 i

Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, Specimen F

f t-lb mils

, Percent Shear MB2

-100 2.5 4.5 0-MC5

-60 2.5 2.5 0

i MC6

-20 30.0 29.0 2

MCL 30 52.5 50.5

.30 MAC 55 43.5 41.0 40 MCJ 80 70.0 54.0 75-1 MC7 145 93.0 75.5 90.

MCU 212 97.5 80.5 100

.i I

a f

^

4 29 TABLE 10. CHARPY V-NOTCH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO.1 ESW HAZ METAL FROM CAPSULE G1 Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, Specimen F

f t-lb mils Percent Shear MKE

-20 9.0' 6.0-5 MLD 30 17.5 17.0 10 MK4 55 29.5 27.5 15

~

MLA 80 31.0 23.5 20 ML4 115 60.0 55.0 50 MLK 145 46.5 45.5 55' MPE 212 67.0 60.0 85 a

MKT 300 83.5 57.5 100 TABLE 11. CHARPY V-NOICH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO.1 ESW HAZ METAL FROM CAPSULE C2 Test Impact Lateral Frac ture Temperature, Energy,.

Expansion,

-~ Appearance, Specimen F

f t-lb mils Percent Shear MMC

-100 3.0 4.5 0

MM6

-60 31.0 23.0 15 MMB

-20 26.0 22.5 10 MKA 30 119.0 86.5 100 MM7 55 116.0 78.0 90 MM5 80 118.5 84.0 100 r

MK5 145 131.5 85.0 100 MMD 212 127.5 80.0 100 Y

i a

l l

30 TABLE 12. CHARPY V-NOICH IMPACT TEST RESULTS FOR QUAD CITIES l

UNIT 1 SAW WELD METAL FROM CAPSULE G1 f

Test Impact Lateral Fracture i

Temperature,

Energy, Expansion, Appearance, Specimen F

ft-lb mils Percent Shear P1K

-20 5.0 6.0 5

P2Y 30 12.5 12.0 10 P4K 80 20.5 22.0 30 P3T 145 34.5 24.0 55 P36 212 44.0 41.5 90 P3K 300 36.0 39.0 100 P15 300 46.0 41.0 100 P22 350 52.0 58.0 100 TABLE 13.

CHARPY V-NOICH IMPACT TEST RESULTS FOR QUAD CITIES UNIT NO.1 SAW HAZ METAL FROM CAPSULE G1 i

Test Impact Lateral Fracture Temperature,

Energy, Expansion,

, Appearance, Specimen F

ft-lb mils Percent Shear i

P7B

-20 12.5 11.0' 10 P6Y 30 35.0 30.0 35 PAM 80 35.0 36.0 50 P63 125 48 42.0 85 P7Y 145 70.5 65.0 100 PAB 212 55.0 43.0 100 PAU 300 65.5 70.0 100 P7A 350 59.0 58.0 100 l

t f

31-i i

i 15 0 i

i

-O- -Unirradiated O -Capsule G2 e -Capsule G1 j

t, O

U i

O i

@ 10 0

=

o e

a C

w O

di z

O w

s i

O 4

i E

O o

25 50 t

a-O O

oo o

t O

l

-10 0 0

10 0 200 300!

TEMPERATURE, F FIGURE 11. CHARPY IMPACT ENERGY VERSUS TDiPERATURE FOR '

QUAD CITIES UNIT NO.1 BASE METAL

.f i

1

32 t

15 0 i

i i

-o-- Unirradialed 0 - Capsule G2

-o--Capsule G1 O

y100

[cP a

a w

Cr*

wz W

D a

o f

E D

- 50 O

o O

o a

C O

-10 0 0

10 0 200 300.

TEMPERATURE, F FIGURE 12.

Cl&RPY IMPACT ENERGY VERSUS TEMPERATURE FOR QUAD CITIES UNIT NO.1 ESW WELD METAL l

i

4 33 15 0 -

i o -Unirradiated D-Capsule G2 g

-fr - Capsule G1 O

t U

O O

9100 E

~

>-g n-La5 s

O A

N O

a o_

E 50 O

a O

O o

3 O

c 9

9 i

e i

-10 0 0

10 0 200 300 '

TEMPERATURE, F FIGURE 13.

CHARPY IMPACT ENERGY VERSUS TDiPERATURE FOR QUAD CITIES UNIT NO. 1 ESW llAZ FITAL f

P G

l 34 i

10 0 i

f O' Unirradiated j

A-Capsula G1

]

80 o

O 2

o

- 60

>r o

i rr

'1!

ji. ;

.i 5

a F-W 40 o-i a

_s.

g I

20 c

_q 1

0

-10 0

-50 0

50 10 0 15 0 200 250

'300 350 '

TEMPERATURE, F FIGURE 14 CHARPY Il! PACT DIERGY VERSUS TDiPERATURE FOR QUAD CITIES l

UNIT NO.1 SAW WELD HETAL 1

i i

35 15 0 i

O-Unirradiated a-Capsule G1 O

e 100 E-

>ocr wzW O

A i--

O A

u a

f a

E 50 O

O

(

0

-10 0

-50 0

50 10 0 15 0 200 250 300 350 i

TEMPERATURE, F j

j TIGURE 15.

CHARPY IMPACT D4ERGY VERSUS TDiPERATURE FOR QUAD CITIES j

UNIT NO.1 SAW EAZ METAL

l l

l l

36 l

i i

M4L M4U M4K M4M l

EIR ed RE M i

i.

JM.4 E

M5Y M57 M3E M3D 1

1 FIGURE 16.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES i

i FOR QUAD CITIES UNIT NO. 1 IRRADIATED l

j BASE METAL FROM CAPSULE G1

)

t l

1 M36 M3B M4B M5L j

.I l

[ [ '

s y.+

fti

l si -

i 1, ~

k; 2.

\\

~ g-t M4E M24 M22 MSP FIGURE 17.

CHARPY IMPACT SPECIMEN FRACTURE St% FACES FOR QUAD CITIES UNIT NO.1 IRRADIATED BASE METAL FROM CAPSULE G2

37 M7U MDB M7K MAM

.fiYh Y'

{'$ht'

<Y: :=; pu e-

't f,

.a,

da, t

M7M M7Y MA6 MD7 FIGURE 18. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO.1 IRRADIATED ESW WELD METAL FROM CAPSULE G1 l

MB2 MC'S MC6 MCL 1

.M-

.}

S

~., y*

T +.

v.

e-

$ 0; Y. /

f

1. %# 4

%e MAC MCJ MC7 MCU FIGURE 19. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT 10 1 IRRADIATED ESW WELD METAL FROM CAPSULE G2 l

u_

i' 38 i

4 i

MKE MLD MK4 MLA 1

l

'g

./ h>$.

d.:

c..

.v...

ag.g

. ~

j 1

1 l

\\

y

-c..

.8 9,.

i ML4 MLK MPE MKT l

a FIGURE 20.

CIRRPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES L' NIT NO.1 IRRADIATED ESW IRZ METAL FROM CAPSULE G1 1

j r

t i

i l

MML MM6 MMB MKA J

l l

l

' s..

i

1. 4 i

y*

l

'.? :4 1

a

?

g-8 9) t

. ~.

\\

i MM7 MMS MK5 MP3 l

1 FIGURE 21.

CIRRPY IMPACT SPIEIMEN FRACIURE SURFACES

[

FOR QUAD CITIES UNIT NO.1 IRRADIATED ESW IRZ METAL FRai CAPSULE G2 1

l 4

i i

d 1

J m-,,

.--... -w.,m-

r i

39 L

t i

P1K P2Y P4K P3T l

kU:..

p gd[

4 i

g te; 2

n l'

.f g

n i'

9W l.'

y.

4 i

l

~;%'

i

)

i

[

t P36 P3K P15 P22

?

e i

r l

FIGURE 22. CHARPY IMPACT SPECIMEN FRACTURE SURFACES l

FOR QUAD CITIES UNIT NO 1 IRRADIATED l

SAW WELD METAL FROM CAPSULE G1

)

i i

j J

r i

l P7B P6Y PAM P63 l

>=

!6 f

• [p.

.)

s.+

5 sf-

-,v

., y.,

)

h.-

a t

l j

.,0

'4. $ ;,.

.+

l sy j

(@

43

)

5 1

i a

P7Y PAB PAU P7A t

l FIGURE 23. CHARPY IMPACT SPICIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 1 IRRADIATED SAW HAZ METAL FROM CAPSULE G1 t

i

.e s

l 40 l-i As the test temperature is increased, specimens show an increasing amount l

of shear fracture appearance. The +300 F specimen (M3D) fracture surface t

is typical of the type seen at the higher temperature end of the Charpy transition curve. The fracture surface shows large shear lips with a 1007. shear f racture appearance. The specimen absorbed the relatively large amount of 81.5 f t-lb during impact. The substantial amount of

'l plastic deformation occurring during this test is reflected in the large value of 67.5 mils lateral expansion.

l J

Table 14 summarizes the 30 and 50 f t-lb transition temperature and the upper shelf energy. The unirradiated values for the base, ESW weld, and ESW IRZ materials are very close to the corresponding three materials l

which were irradiated in Capsule G2.

(A 30 f t-lb transition temperature

{

value is not listed for Capsule G2 ESW weld metal because of the relatively f

few data points in this energy range.) This is consistent with predictions made when the surveillance program was originally set up, and is due to the irradiation level for Capsule G2 specimens being too low to cause any appreciable impact property changes.

In contrast to the Capsule G2 results, the impact properties of I

~

the Capsule G1 specimens have been significantly shif ted due to the relatively high level of irradiation of this capsule. The 50 f t-ib transition temperature ranges from +135 to +150 for all Capsule G1 materials except the SAW weld metal, which has a value above 300 F.

Table 15 is a comparison of the unirradiated and Capsule G150 f t-lb transition temperature behavior. The lowest shif t is the ESW weld metal change from l

an unirradiated value of +35 F to an irradiated value of +140 F, a e

transition temperature increase of 105 F.

The base, ESW HAZ, and SAW 1%Z metals all have 50 ft-lb transition temperature increases in the 130 to 140 F l

range.

The largest increase is the change from an unirradiated value'of l

+20 F to an irradiated value of above 300 F for the SAW weld metal, a change of greater than 280 F.

This large chartge is a result of the drop in upper shelf energy to a value only slightly greater than 50 f t-lb, as can be seen in Figure 12.

1 l

I 41 I

l 1

i TABLE 14. CRARPY IMPACT PROPERTIES FOR QUAD CITIES UNIT NO. 1 l

i 30 f t-lb 50 ft-Ib Upper Shelf, Material Capsule TT, F TT, F f t-lb Base Unirradiated

-30 0

105 Base C2

-40

+10 105 Base C1

+95

+135 85 ESW Weld Unirradiated

+10

+35

>100 ESW Weld G2

+10

+40 95 ESW Weld G1

+90

+140 85 i

ESW HAZ Unirradiated

-20

+5 115 i

ESW HAZ G2

- 40

- 10 125 i

ESW HAZ G1

+70

+135 80 SAW Weld Unirradiated

-30

+20 72 f

SAW Weld G1

+125

>300 52 SAW HAZ Unirradiated

-30

+10

~100 SAW HAZ G1

+40

+150 60

.i l

~

=::t l

1 J

l

i l

1 i

42

-)

TABLE 15.

COMPARISON OF QUAD CITIES UNIT NO. 1 UNIRRADIATED AND IRRADIATED (CAPSULE GI) 50 ft-lb TRANSITION TDiPERATURE BEHAVIOR Capsule G1 l

Unirradiated Irradiated ATT i

Material TT, F TT, F F

Base 0

+135 135 ESW Weld

+35

+140 105 ESW HAZ

+5

+135 13 0 SAW Weld

+20

>300

>280 SAW HAZ

+10

+150 140 I

l i

i i

e t

i l

l h

I e

r I

43 i

The upper shelf energy of a Charpy impact curve is defined as

[

the upper level of energy that curves exhibit at higher temperatures where

{

increases in test temperature cause no further increase in impact energy.

l A general effect of irradiation is to lower the upper shelf energy. The i

upper shelf energy level for Capsule G1 specimens ranges from relatively i

low values of 52 and 60 ft-lb for SAW weld and SAW RAZ metals to higher I

values in the range of 80 to 85 ft-lb for the base, ESW weld, and ESW f

I HAZ metals.

As discussed earlier, the four Charpy capsules from capsule basket

-l assembly No. 2 (Capsule GI) did not receive uniform neutron exposure.

(

18 t

The exposure based on the iron dosimeters ranged from 4.8 x 10 to

{

18 11.9 x 10 nyt (>l Mev). For discussion purposes, an average value of the four iron dosimeters of 8.2 x 10 nyt can be used. However, particular f

exposure values can be assigned to each of the five materials, since specimens of each material were in either one or two capsules. Those specimens of a particular material located in two capsules were always in adjacent capsules.

Using a conservative approach of assigning the lowest neutron exposure received by any specimens of a.particular material, 18 the five materials received exposures as follows: base, 11.,9 x 10 nvt; i

18 18 18 ESW weld, 8.9 x 10 nvt; ESW HAZ, 8.9 x 10 nyt; SAW weld, 7.2 x 10 nyt; f

18 SAW HAZ, 4.8 x 10 nyt.

Transition temperature values used in following

.t figures are plotted based on these exposures.

I The transition temperature shifts for the irradiated materials are shown plotted in Figures 24, 25A, and 25B as a function of fluence.

Figure 24 is the 30 f t-lb shif t curve from the General Electric surveillance program report (8)

Figure 25A is the 30 f t-lb shif t, and Figure 25B is the j

50 f t-lb shif t values obtained in other surveillance programs and the present

}

( ~ )

program.

The SAW weld 50 It-lb transition temperature value of >280 F l

is not shown in Figure 25B. The apparent large scatter in data among the' l

various programs is not unusual. Note that the weld-metal values generally l

determine the upper bound of the trend band. The values used to form the j

trend band are those from programs where the irradiation temperature was j

betweea 550 and 590 F.

It can be seen that the five transition temperature

)

a.

'44 CENERAL ELECTRIC SURVEILLANCE PROGRAM TEST RESULTS PLOTTED FOR COMPARISON WITH REFERENCE DATA h DNPS-BASE t.tETAL C HUMBOLDT-DASE METAL h DNPS-WELD fAETAL

+ HUMBOLDT-WELD tAET AL h DNPS-HAZ

<> HUMBOLDT - HAZ O Bic ROCK - BASE NETAL 9 BIG ROCK -WELD METAL G BIG ROCK -HAZ 650 i

e i s ung i si mg i i i a song i i e siusg i a 4 a asaan EXPERIMENT 600 NATERIAL CDDE A

B C

D E

14,6,7 9

O O

O 550 12 V

V 13 A

A A

15, 8, 9 E

D W

g e

500 11 X

5 i*u A

U 450 e:

• • WORST-CASE **

R ATT = 12223 - 1475 LOG ($t) +44.5 (LOG ($t2 f 400 3 1.75 x 10 A D 0 " 350 225 F g 5 PNPS BASE t.tETAL E e E 300 } g UPPER LIMIT FOR t-550*F GE-BWR S OPERATING EXPERtENCE g g 4-e - 200 E e A N 5 150 V QD GO 4 'h A 1 00 O AA 50 D B e,,,, i9,1l .,,,,,l ,,,,,,,,li,,,,,,,, tt 20 16 17 is - 3o 30 1021 10 30 3g INTECRATED NEUTRON DDSAGE ( > 1 MeV) ($t), twt FIGURE 24 THE EFFECT OF IRRADIATION ON VARIOUS HEATS OF A302B/A533B (AFTER BRANDT AND HIGGINS)

45 I i i iiiiil l l 1 1 l l i1l Base Weld HAZ Point Beach No.1 O + 4 Connecticut Yankee O G 300 Big Rock Point V V V Humbolt Boy C> Son Onofre 4 4 Dresden No.3 EF E E Quod Cities No.1 d 4 Q Yankee Surveillance 6 Yankee Special O Y E -m 200 b.s g V Y E E# 8 A 10 0 6 o Q d V Y E-Trend Band For 550-590 F 0 m1 I I !IIl I i I I I IiIl ~' 10'8 10'S 1020 Neutron Fluence,nyt FIGtmE 25A. COMPARISON OF 30 FT-LB TR/JiSITION TDIPERATLUtE VALUES FROM VARIOUS SURVEILLANCE PROGPJetS FOR A302 CRADE E PRESSURE VESSEL STEEL

i 46 i i i i i iisii) i i ie i.s i ) Base Weld HAZ Point Beach No.1 Q Connecticut Yankee o e e 300 H.B. Robinson D Dresden No.3 D-E- E Quod Cities No.1 D 8 d u. E o .5 e g200 e a> a. E& g E' + ce E; gD i o. M' .a t - 100 e o" O o o G $a' R o O D i I I 0 10'8 10'8 10 ( 20 Neutron Fluence,nyt FIGURE 25B, COMPARISON OF 50 FT-LB TRANSITION TDiPERATURE SHIFT VALUES FROM VARIOUS SURVEILIJd3CE PROGRAMS FOR SA302 GRADE B PRESSURE VESSEL MATERIALS

47 L shift values for the pressure vessel materials of the present program fall within the Figure 25A upper and lower bounds determined by materials of other investigations. t Hardness Pronerties j Rockwell B hardness < measurements were made on all caterials for. each of the two capsules. Hardness measurements were made on three I specimens for each material. Table 16 lists the individual readings and the average readings. Table 17 is a comparison of the irradiated results from this program with the unirradiated results from the base line program. ( ) Lu:h value in the table is an average of 15 hardness readings, calculated from five readings per specimen on a group of three specimens. As expected, the average hardt.ess of unirradiated and Capsule G2 specimens for a particular material are essentially identical because of the low neutron fluence of Capsule G2 specimens. However, the average hardness of Capsule G1 specimens in comparison to that of the unirradiated specimens is t appreciably increased for each of the five materials. This^is typical behavior for pressure vessel steel after appreciable irradiation. f i e

48 TABLE 16. HARDNESS RESULTS FOR QUAD CITIES UNIT NO.1 SPECIMDiS ~ Individual Readings. Rockwel? B

Average, Material Capsule Specimen No. 1 No. 2 No. 3 No. 4 No. 5 Rockwell B base G2 M5L 91.2 90.7 92.7 89.7 91.4 91.1 Base C2 M4E 91.1 94.2 89.8 90.4 91.8 91.5 Base C2 M36 90.8 90.3 89.4 91.0 91.8 90.7 Base G1 M3D 97.3 96.5 96.4 98.0 99.1 97.5 Base G1 M3E 97.8 97.3 97.3 98.0 98.0 97.7 Base G1 MAL 98.7 98.2 97.8 97.4 97.3 97.9 ESW Weld G2 MB2 89.3 89.7 89.2 89.6 89.3 89.4 ESW Weld G2 MAC 87.9 87.7 88.1 88.1 89.2 88.2 ESW Weld G2 MCL 90.8 91.2 91.3 89.2 89.5 90.4 ESW Weld G1 M7U 92.4 92.4 92.6 93.8 93.4 92.9 ESW Weld G1 MDB 94.6 95.1 95.8 94.4 94.4 94.9 4

ESW Weld G1 M7K 93.5 94.5 94.0 93.8 94.4 94.0 ESW HAZ G2 MKA 86.4 86.0 87.3 87.9 88.0 87.1 ESW HAZ G2 MMD 89.8 90.0 91.1 93.1 91.8 91.2 ESW HAZ G2 MM7 88.0 88.7 88.3 88.1 88.7 88.4 ESW HAZ G1 MLD 96.1 96.7 93.8 94.3 95.0 95.2 ESW HAZ G1 MKE 92.5 94.0 93.9 95.0 94.0 93.9 ESW HAZ G1 MPE 96.1 95.2 94.7 95.7 94.8 95.3 SAW Weld G1 P3T 100.0 100.0 98.8 98.3 98.3 99.1 ~ SAW Weld G1 P22 94.0 95.2 93.8 97.4 98.9 95.9 SAW Weld G1 P1K 98.4 98.8 98.7 99.3 99.3 98.9 SAW HAZ G1 P7Y 98.7 99.0 99.8 99.4 99.1 99.2 SAW MAZ G1 P63 98.7 98.3 98.5 97.3 98.7 98.3 SAW HAZ G1 PAB 98.7 99.0 98.1 98.8 98.8 98.7 O /

49 1 ) b TABLE 17. COMPARISON OF UNIRRADIATED AhT IRRADIATED AVERAGE HARDNESS RESULTS FOR QUAD CITIES - j UNIT NO.1 SPECIMENS - i Average Hardness,(#) [ Material Capsule' Rockwell B Base Unirradiated 92.0 Base Capsule G2 91.1 Base Capsule G1 97.7 ESW Weld Unirradiated 88.9 ESW Weld Capsule'G2 89.3 ESW Weld Capsule G1 93.9 ESW HAZ Unirradiated 88.2 [ ESW HAZ Capsule G2 88.9 ESW HAZ Capsule G1 94.8 SAW Weld Unitradiated 92.4 1, I SAW Weld Capsule G1 98.0 SAW HAZ Unirradiated 91.1 i SAW HAZ Capsule G1 98.7 i (a) Average of three specimens, five hardness readings per specimen. i 1 i I ( [ i Y -r, n n w ,-,e-e- -r,,- --- - r n

50 Tensile Pronerties The tensile properties determined are listed in Table 18. The table lists temperature, 0.2 percent offset yield strength, ultimate tensile strength, uniform elongation, total elongation, and reduction in area. The identification number on the end of one of the tensile specimens was obliterated during removal from its tensile capsule. The other specimen in the capsule was PJD. The identity of the first specimen is inferred to be PJU based on the General Electric specimen f inventory which shows PJD paired with PJU in a tensile capsule.( ) ^ Posttest photographs of the tensile specimens are shown in Figures 26 through 29. These photographs show the necked down region of the gage length and the fracture. A typical tensile test curve is [ shown in Figure 30; the particular test shown is for base metal Specimen l PD6 tested at room temperature. Tensile tests were run at room temperature and 550 F. The higher temperature tests exhibited a decrease in 0.2 percent offset t yield strength and a decrease in ultimate tensile strength for each material. In general, ductility values (as determined by total elonga-tion and reduction in area) decreased at 550 F as compared to 75 F for I each material. i The Capsule G1 tensile specimens were located in the vicinity 18 of iron dosimeters which received fluences of 8.91 x 10 and 11.9 x 10 nyt, while the Capsule G2 tensile specimens were located in the vicinity 6 of an iron dosimeter receiving a fluence of 1.0 x 10 nyt (E > 1 Mev). Tensile specimens from Capsule G2 show no significant changes in tensile properties with respect to unirradiated tensile properties. Tensile specimens from Capsule G1, irradiated to a substantially higher fluence, show appreciable property changes. The Capsule G1 yield and ultimate tensile strengths are markedly increased as compared to preirradiation and Capsule C2 values. The total elongation and reduction in area values are the same or moderately less than pre-irradiation and Capsule G2 values.

i l I 51 i TABLE 18. TENSILE PROPERTIES OP QUAD CITIES UNIT NO.1 IRRADIATED SPECIMENS l l 0.27. 'i Offset Ultimate Yield Tensile Uniform Total Reductic ! Temp, Strength, S trength, Elongation, Elongation, in Arer{ Materi al Capsule Specimen F psi psi percent percent percent! Base G2 PDT RT 70,990 93,100 7.1 17.5 69.6 ; Base G2 PDD 550 60,730 88,660 5.9 15.3 59.7 l ESW Weld C2 PJU RT 66,390 84,950 8.3 17.7 68.0 ESW Weld G2 PJD 550 59,430 84,220 7.3 16.8 59.6 ESW EAZ G2 PLB RT 65,580 85,340 6.8 16.5 65.8-l ESW HAZ G2 PLK 550 58,200 81,350 6.3 15.1 63.9 j Base G1 PD6 RT 92,260 111,610 7.8 15.4 61.1 p Ease G1 PDM 550 78,620 103,460 7.2 15.1 56.8' ESW Weld G1 PJ3 RT 75,980 94,660 9.0 17.6 63.2 ESW Weld G1 PJ6 550 70,790 93,310 7.1 14.5 53.0 i ESU HAZ G1 PLC RT 78,850 96,710 6'.1 13.5 64.7 ESU HAZ G1 PLD 550 68,570 90,820 6.1 14.0 54.9 SAW Weld G1 PPB RT 94,690 109,800 8.8 17.4 57.1 i SAW Weld G1 PPJ 550 83,540 101,630 7.8 14.8 49.4 I SAW HAZ G1 PU5 RT 97,350 112,240 7.6 14.4 51.4 SAW HAZ G1 PUM 550 80,080 101,220 5.8 12.8 53.3 i I I r 6 6 -i i r

s i j 52 i Material: Base Capsule: G2 'T Specimen: PDT Test Temperature: RT m = yght ** w t 4 1 Material: Base Capsule: G2 Specimen: PDD q Test Temperature: 550 F l l l l Material: ESW Weld l Capsule: G2 ,y l Specimen: PJU l Test Temperature: RT W. a Q.; s '"'46. ~4kQ%rj. i l l 1 1 Material: ESW Weld j Capsule: G2 l Specimen: PJD Test Temperature: 550 F l i l ) i FIGURE 26. POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO.1 l IRRADIATED TENSILE SPIEIMENS i l lL

l I i 53 i i l l Material: ESW HAZ l Capsule: G2 l Specimen: PLB Test Temperature: RT &.d'" g. i A l \\ I Material: ESW HAZ l Capsule: G2 Specirnen: PLK l Test Temperature: 550 F I I i i I j Material: Base Capsule: G1 l 'f Specimen: PD6 y.: Test Temperature: RT l l l l l Material: Base Capsulet G1 i i Specimen: PDM Test Temperature: 550 F l l 1 a l FIGURE 27. POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 1 l ' IRRADIATED TENSILE SPIEIMENS 3 l i i

54 4 i k a 1 Material: ESW Weld ^ Capsule: G1 Specimen: PJ3 l Test Temperature: RT k NW

fri, i

i l l i i Material: ESW Weld { Capsule: Gl. Specimen: PJ6 ( Test Temperature: 550 F ) J i 1 Material: ESW HAZ Capsule: G1 ,er: Specimen: PL6 l e Test Temperature: RT y-r* l l l l Material: ESW HAZ l Capsule: G1 i Specimen: PLD l Test Temperature: 550 F l l i l r I t l F IGl'RE 2 8. POSTTEST PHOIDGRAPHS OF QUAD CITIES UNIT NO.1 l IRRADIATED TENSILE SPECIMDiS

l l

l l

1 ? a i 55 I s i i l i Material: SAW Weld i Capsule: G1 i 1 Specimen: PPB l

• )D;+r y

Test Temperature: RT i i J a j 1 l Material: SAW Weld } Capsule: G1 i Specimen: PPJ Test Temperature: 550 F l k 1 i I l l 1 l l Material: SAW HAZ Capsule: G1 y Specimen: PUS c. Test Temperature: RT j

• %we*

l t I i I l Material: SAW HAZ Capsule: G1 Specimen: PUM i Test Temperature: 550 F - v e,. ~ i b l FIGURE 29. POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 1 IRRADIATED TENSILE SPECIFES I

h 56 t i i 125,00g l 8 i .i 100,000 t k 75,000 u> O co i en tu T 1 b 50,000 'l 25,000' - i I 0-I I O 5 10 15 20 25 PERCENT ELONGATION,in/in FIGURE 30. TfPICAL S'IRESS-SIRAIN CURVE Curve shout is for base metal specimen PD6 tested at RT. e t <,,,,,-,---.---4 =--s- --*+ * ' + " - ' " ' * * * *

• F 59 (13) ASIH Designation E523, " Measuring Fast Neutron' Flux by Radioactivation of Copper", under preparation for publishing in Book of ASTM Standards, Part 45.

(14) ASTM Designation E23-72, " Notched Bar Impact Testing of Metallic Materials", Book of ASTM Standards, Part 10 (1974), pp 167-183 (15) ASTM Designation A370-73, " Mechanical Testing of Steel Products", Book of ASTM Standards, Part 10 (1974), pp 1-52 (16) Brasher, W. S., and Timmons, D. H., " Comparative Analysis of the Pressure Vessel Surveillance Requirements for Commonwealth Edison l Power Reactors", Final Report to Commonwealth Edison Company (November 1,1974). 1 (17) Serpan, C. Z., Jr., and Watson, H. E., " Mechanical Property and Neutron Spectral Analyses of the Big Rock Point Reactor Pressure Vessel", Nucl. Eng. Design, 11, 393-415 (1970). t (18) Serpan, C. Z., Jr., and Hawthorne, J. R., " Yankee Reactor Pressure-Vessel Surveillance: Notch Ductility Performance of Vessel Steel and Maximum Service Fluence Determined from Exposure During Cores II, III, i and IV", NRL Report 6616 (September 29, 1967). 1 (19) Brandt, F. A., "Humboldt Bay Power Plant Unit No. 3 Reactor Vessel Steel i Surveillance Prograd', CECR-5492 (May,1967). L (20)." Analysis of First Surveillance Material Capsule from San Onofre Unit 1", Southern California Edison Company (July,1971). - (21) Perrin, J. S., Sheckherd, J. W., and Scotti, V. G., " Examination and Evaluation of Capsule F for the Connecticut Yankee Ractor Pressure-Vessel Surveillance Program'", Final Report to Connecticut Yankee Atomic Power Company (March 30, 1972). (22) Perrin, J. S., Sheckherd, J. W., Farmelo, D. R., and Lowry, L. M., " Point Beach Nuclear Plant Unit No.1 Pressure Vessel Surveillance Program: Evaluation of Capsule V", Final Report to Wisconsin Electric Power Company (June 15, 1973). l (23) Perrin, J. S., Farmelo, D. R., Denning, R. S., and Lowry, L. M., "Dresden Nuclear Plant Unit No. 3 Reactor Pressure Vessel Surveillance i Program: Capsule Basket No. 13, Capsule Basket No. 14, and Neutron Dosimeter Monitor", Final Report to Commonwealth Edison Company (March 1, 1975). (24) Yanichko, S. E., Lege, D. J., Anderson, S. L., and Mager, T. R., " Analysis of Capsule S irom Carolina Power and Light Co. H.B. Robinson Unit No. 2 Reactor Vessel Radiation Surveillance Program", Final Report to Carolina Power and Light Co. (December, 1973). i i

~, } 1 i 57 l CONCLUSIONS f i The average neutron exposures received by Capsules G2 and G1 f 16 18 were 1.0 x 10 nyt (>l MeV) and 8.2 x 10 nvt (>l MeV), respectively. The shift in the 30 f t-lb and 50 f t-lb transition temperature and the upper shelf energy were determined for base metal, submerged-arc-veld weld (SAW weld) metal, submerged-arc-weld heat-affected-zone (SAW HAZ) metal, electro-slag-weld weld,(ISW weld) metal, and electro-slag-weld i heat-affected-zone (ESW HAZ) metal. Capsule G2 values were essentially unchanged because of the relatively low fluence of these specimens. The. l [ 50 f t-lb transition temperature is in the range of 135 to 150 F for all Capsule G1 materials except the SAW weld metal which has a value of above 300 F. The upper shelf energy level of Capsule G1 materials ranges from 52 to 85 f t-lb, with the value of 52 f t-lb being for the SAW weld metal. .l Hardness properties of Capsule G2 materials were essentially { unchanged by irradiation, but Capsule G1 materials. all shou increases. Tensile properties of Capsule G2 specimens were essentially l t unchanged by irradiation. However, tensile properties of Capsule G1 s specimens showed significant changes. Both yield strength and ultimate tensile strength values are significantly higher as a result-of irradiation. { I s a t i i P h 1 f ) t I

i 1 58 i REFERENCES b (1) Reuther, T. C., and Zwilsky, K. M., "The Effects of Neutron Irradiation on the Toughness and Ductility of Steels", in Proceedines of Toward Trnroved Ductility and Touchness Svenostus, published by Iron and i Steel Institute of Japan (October, 1971), pp 289-319. (2) Steele, L. E., " Major Factors Affecting Neutron Irradiation Embrittle-ment of Pressure-Vessel Steels and Weldments", NRL Report 7176 (October 30, 1970). i (3) Berggren, R. G., " Critical Factors in the Interpretation of Radiation j Effects on the Mechanical Properties of Structural Metals", Welding l Research Council Bulletin, 32, 1 (1963). (4) Witt, F. J., "Haavy-Section Steel Technology Program Semiannual Progress l Report for Period Ending February 29, 1972", ORNL Report No. 4816 (October, 1972). (5) Hawthorne, J. R., " Radiation Effects Information Generated on the ASTM I Reference Correlation-Monitor Steels", American Society for Testing and Materials Data Series Publication DS54 (1974), i (6) Steele, L. E., and Serpan, C. Z., " Neutron Embrittlement of Pressure f Vessel Steels - A Brief Review", Analysis of Reactor Vessel Radiation Effects Surveillance Programs, American Society for Testing and Materials Special Technical Publication 481 (1969), pp "47-102 (7) Integrity of Reactor Vessels for Light-Water Power Reactors, Report by the USAEC Advisory Committee on Reactor Safeguards (January,1974). I t r (8) Higgins, J. P., and Brandt, F. A., " Mechanical Property Surveillance of General Electric BWR Vessels", General Electric Report NED0-10115 (July, 1969). I (9) ASI11 Designation E185-73, " Surveillance Tests on Structural Materials in Nuclear Reactors", Book of ASTM Standards, Part 45 (1974), pp 621-627. (10) Perrin, J. S., and Lowry, L. M., " Quad Cities Nuclear Plant Unit No. I and Unit No. 2 Reactor Pressure Vessel Surveillance Programs: Un-irradiated Mechanical Properties", Final Report to Commonwealth Edison Company (February 15, 1975). L (11) ASTM Designation E263-70, " Measuring Fast Neutron Flux by Radioactivation I of Iron", Book of AST11 Standards, Part 45 (1974), pp 814-819. (12) ASTM Designation E264-70, " Measuring Fast Neutron Flux by Radioactivation of Nickel", Book of ASTM Standards, Part 45 (1974), pp 820-824 l i I i

t O i.! i D ? 1 'T [ t 1 + !. i i e t APPENDIX A b INSTRUMENTED CHARPY EXAMINATION a \\; 4 9 9 ? 3 I 4 h s 1 I s 4 4 1 ) i J l l ~ l i I i l 1 -l 4 ~) g

l i APPENDIX A INSTRUMENTED CHARPY EXAMINATION i INTRODUCTION The radiation embrittlement of an operating nuclear pressure vessel is determined by the accelerated irradiation of the original materials as part of a surveillance program. The lifetime of the pressure vessel will i depend on the radiation-induced shift in the ductile-brittle transition temperature as measured by the Charpy V-notch impact test. The value of baseline unirradiated and irradiated Charpy impact specimens, particularly in present surveillance programs, can be enhanced by the use of the instrumented Charpy test. The instrumented Charpy test provides a link between the transition-temperature approach and the fracture-mechanics approach to fracture toughness. The results obtained by applying instrumented Charpy techniques to the unirradiated Charpy specimens for the surveillance program are presented in this section of the report. BACKGROUND There are two approaches to determining the effect of radiation on the fracture toughness of pressure-vessel steels: (1) the shif t in the ductile-brittle transition temperature, and (2) the change in the fracture toughness (either the static f racture toughness K r the dynamic fracture Ie toughness (rid). The nodern theories of fracture define key metallurgical fracture parameters such as friction stress, grain size, grain-size dependence. of the yield stress, and surface energy or plastic work of microcrack 1 propagation. The effect of radiation on most of these netallurgical fracture parameters has been previously studied, but until recently, the results had not been directly linked with the radiation-induced change in fracture toughness. This recent work established the relationships between the key metallurgical fracture parameters and the transition temperature and K ()* 7j f t

• References at the end of this Appendix.

.;J

A-2 .j i The instrumented Charpy test is an excellent tool for determi- ~ nation of the effects of radiat.on on the key metallurgical fracture j i parameters. This test provides load-time information in addition to the j energy absorbed. The loads involved during impact are obtained by instru-menting the Charpy striker with strain gages so that the striker or tup i is essentially a load cell. The details of this technique have been

• )

reported previously. The additional information obtained from the instrumented Charpy - i i GY (P astic yielding across the entire l test is the general yield load, P cross section of the Charpy specimen), the maximum load, P,,x, the brittle fracture load, P, and the time to brittle fracture (see Figure A-1). The F area under the load-time curve corresponds to the total energy absorbed, [ which is the only data obtained in a normal uninstrumented Charpy test. The instrumented test, however, allows separation of the energy absorbed into (1) the energy required to initiate ductile or brittle fracture (premaximum load energy), (2) the energy required for ductile tearing (postmaximum load energy), and (3) the energy associated with shear lip I formation (postbrittle fracture energy), as shown in Figure A-1._ In a normal Charpy impact study, the energy absorbed is determined as a function of temperature to obtain the Charpy impact curve and the transition temperature. The instrumented Charpy test also gives the information shown in Figure A-1 as a function of temperature, as shown by i the example in Figure A-2. Various investigatorsf ~ ) have deve' loped i theories that permit a detailed analysis of the load-temperature diagram. This diagram can be divided into four regions of fracture behavior, as shown in Figure A-2. In each region different fracture parameters are involved (2), Extended discussions of these fracture parameters can be found in the j references indicated above. s b h r

b A-3. i 4 1 -Maximum load, P ' 7 General yield \\-- max load, P _ cy j Brittle fracture load, Pp i Post" maximum-load" energy } Post brittle-fracture N energy i PRE" maximum-load" energy ~ j Time to brittle fracture Time i s i FIGURE A-1. AN IDEALIZED LOAD-TDiE HISTORY FOR A CHARPY DiPACT TEST [ 1 I I t t 5 b l 1

A-4 i a i r i 7 e o %s%* u u %g g P e P max' g p u o s, e i F p CY oe -c. c.< Region 1 Region 2 Region 3 Region'4 Test temperature e h i F FIGURE A-2. GRAPHICAL ANALYSIS OF CllARPY IMPACT DATA i t

A-5 EXPERIMENTAL PROCEDURES The general procedures for the instrumented Charpy test are the same as those for the conventional impact test, and are described in the main text of this report. The additional data are obtained through a fairly simple electronic configuration, as shown in the schematic diagram of Figure A-3. The striker of the Lmpact machine is modified to make it a dynamic load sensor. The modification consists of a four-arm resistance strain gage bridge positioned on the striker to detect the compression loading of the striker during the Lapact loading of the specimen. The com-pressive elastic strain signal resulting from the striker contacting the specimen is conditioned by a high-gain dynamic amplifier and the output is photographed as it develops on the cathode ray tube of an oscilloscope. A previously established calibration method (8) is used to convert the oscillo-graph into a time-load record. The time-load history as a function of test temperature forms the basis for further data analysis. The oscilloscope is triggered by a solid-state device at the correct time to capture the amplifier output signal. RESULTS AND DISCUSSION The instrumented Charpy tests were conducted following the procedures discussed in the main text of this report. Specimens were tested from five materials. These materials were the pressure vessel base metal, submerged-arc-weld weld (SAW weld) metal, submerged-arc-weld heat-affected-zone (SAW HAZ) metal, electro-slag-weld weld (ESW weld) metal, and electro-j slag-weld heat-af fected-zone (ESW HAZ) metal. The results of the instrumented Charpy work with the corresponding load-time records are given in Tables A-1 through A-8. The tables list the specimen numbers, test temperature, impact energy, general yield load, and maximum load. It can readily be observed that the features of the load-time or load-deflection traces change as a function of temperature; however, all tests f all into one of the six distinctive notch-bar I bending classifications shown in Figure A-4.

.~. f A-6 s ~F .' i L .A. i [ ) rr 1 I r 6.. ) (I'i v Bridge balance Oscilloscope and O O amplifier t i i i Shunt Triggering resistance device I i Hammer 3 + Y l i FIGURE A-3. DIAGRAM OF INSTRUMENTATION ASSOCIATED WITH INSTRUMENTED CHARPY EXAMINATION i s 4 -i h i i t

A TABLE A-1. INSTRUMENTED CHARPY IMPACT DATA FOR QUAD CITIES UNIT NO. 1 BASE METAL FROM CAPSULE G1 5000 Specinen No.: M4L 4000 Test Temperature (F): -20 e.3000 Impact Energy (f t-lb): 15.5 j2000 General Yield Load (Pgy)(Ib): 1810 1000 Naximum Load (P )(1b): 4240 0 0 1000 2000 3000 4000 50 Time, pste { i 5000 Specimen No.: M4U 4000 [ Test Temperature (F): +30 e-3000 Impact Energy (f t-lb): 21.0 j2000 General Yield Load (PGY) ): 1000 4190 Maximum Load (Pmax)(1b): 0 0 1000 2000 3000 4000 50t Time, psec Specimen No.: M4K 4000 Test Temperature (F): +55 [: Impact Energy (ft-lb): 27.0 General Yield Load (PGY ( ) 1000 4260 0 Maximum Load (Pmax)(1b): 0 1000 2000 3000 4000 500 Time, psec 5000 Specimen No. : M4M I 4000 f j Test Temperature (F): +80 e. 00 ]2000 Impact Energy (f t-lb): 25.0 General Yield Load (Pgy)(1b): 3120 1000 Ma>:imu a Lond (P,,x)(Ib): 4120 0 0-1000 2000 3000 4000 500C Time, psec i I ~i

4 l A-8 l-j TABLE A-1. (Continued) .i 5000 Specimen No.: M5Y l

4000, Test Temperature (F):

+115 g Inpact Energy- (f t-lb): 32.0 )2000' General Yield Load (Pg7)(1b): 3090 gooo Maximun Load (P,g)(Ib): 4000 0 0 1000 2000 3000 4000 5000 Time, psec 5000 Specinen No.: M57 1 4000 Test Temperature (F): +145 8.3000 f Impact Energy (f t-lb): 55.5 2M \\ General Yield Load (Pgy)(1b): 3000 3000 Maximun load (P )(1b): 4280 0 ~ 3000 4000 5000 0 1000 00 Time, psec 5000 Specimen No.: M3E 4000 /\\ Test Temperature (F): +212 ~ 3000 3 Iepect Energy (f t-lb): 88.0 $2000 1000 x General Yield Load (Pgy)(1b): 2950 Maximum Load (Pnax)(1b): 4100 0 1000 2000 3000 4000 b000 ggme,p3,g 5000 Specimen No.: M3D 4000 8 Test Tc=perature (F): +300 -3000 $2000l \\ Impcet En2rgy (it-lb): 81.5 \\ 1000 General Yield Load (PCY)(ib): 2710 g May.ina, Load (Pmar.) (1b) : 3990 0 1000 2000 3000 4000 5000 Time, psec I

j A-9 TABLE A-2 INSTRUMENTED CHARPY IMPACT DATA FOR l QUAD CITIES UNIT NO. 1 BASE METAL l FROM CAPSULE G2 .j f 5000 Specimen No.: M36 -i 4000 / Test Temperature (F): -100 m 3poo l Impact Energy (ft-lb): 9.5 }2000 f General Yield Load (PCY)(Ib): 3430 1000 Maximu:2 Load (P, )(1b): 3800 0 0 1000 2000 3000 4000 50(X .I Time,psec o i 5000 Specimen No.: M3B g Test Temperature (F): -60 e .3000 Impact Energy (f t-lb): 26.0 }2000 { General Yield Load (Pg7)(1b): 3400 1000 0 1000 2000 3000.4000 5000 f Maximum Load (P )(1b): 4300 0 Time, psec i Specimen No.: M4B 5000l 4000 l [ Test Temperature (F): -20 -m {3000 Impact Energy (f t-lb): 28.5 General Yield Load (Pg7)(1b): 2400 1000 Maximum Load (P, )(1b): 3330 0 0 1000 2000 3000 4000 5000 Tape,psee 5@ Specimen No.: M5L l 4000 Test Temperature (F): +30 g - 3000 Impact Energy (f t-lb): 55.5 3 3 2000 General Yic1d Load (Pg.)(Ib) : 3380 4200 0 --2000 3000 4000 5000-Maximum Load (Pmax)(1b): 0 1000 Tbne, psec i ~

A-10 TABLE A-2 (Continued) Specimen No.: M4E 5000 Test Temperature (F): +55 4000 Impact Energy (f t-lb): 75.0 g3000 3 2000 General Yield Load (Pgy)(1b): 3100 ( Maximum Load (P )(1b): 4050 \\ 0 1000 2000 3000 4000 5000 Time, psec Specimen Eo.: M24 Test Temperature (F): +80 Impact Energy (f t-lb): 80.0 General Yield Load (PGY)(1b): IM Maximum Load (P, )(1b): NA Specimen No.: M22 5000 Test Temperature (F): +'45 4000 g 000 Impact Energy (f t-lb): 108.5 77 ( \\ 2000 General Yield Load (PGY)(1b): 2510 \\ 1000 x Maximum Load (Pmu)(1b): 3930 0 0 1000 2000 3000 4000 5000 Time, psec Specimen No.: MSP 5000 Test Temperature (F): +212 4000 ,3000 '\\ / Impact Energy (f t-lb): 110.5 g 0 2000 General Yield Load (PGY)(Ib): 2460 \\ Mar.imum Load (P )(Ib): 3820 0 0 1000 2000 3000 4000 5000 Time, psec

A-11 TABLE A-3. INSTRUMENTED CHARPY IMPACT DATA FOR QUAD CITIES UNIT NO. 1 ESW WELD METAL FROM CAPSULE G1 i Specimen No.: M7U $000 Test Temperature (F): -20 4000 f.000 3 i Impact Energy (ft-lb): 4.0 ~ General Yield Load (Pgy)(1b): j Maximum Load (P )(1b): 2550 0 0 1000 2000 3000 4000 5000 Time, psec Specimen No.: MDB 5000 4000 Test Temperature (F): +30 3000 Impact Energy (f t-lb): 12.0 g 0 2000 3250 General Yield Load (Pgy)(1b): 3800 Maximum Load (P"#)(1b): 0 0 1000 2000 3000 4000 5000 Time, psec M7K Specimen No.: 4000 Test Temperature (F): +55 g j2000 I= pact Energy (f t-lb): 4.0 General Yield Load (Pgy)(1b): 3000 Maximum Load (P )(1b): 2350 0 0 1000 2000 3000 4000 5000 Time,ysee 5000 Specimen So.: MAM 4000 Test Temperature (F): 460 .3000 Impact Energy (ft-Ib): 26.0 g2000 General Yield Load (PCY)( ): 000 1000 3920 0 11aximum Load (PD3x)(1b): 0 1000 2000 3000 4000 500C Time, pec

l -A-12 TABLE A-3. (Continued) i 5@ [l Specimen No.: M7M 4000 ,/ Test Tecperature (F): +115 .3000 Impact Energy (ft-lb): 45.0 32000 f General Yield Load (?g,)(1b): *2900 1000 i .Maxinus Load (Pmax)(Ib): 4000 o -- _-2000 3000 4000 5000 5 0 1000 Time, psec l j Specinen No.: M6H

)

5@ 4000 Test Temperature (F): +145 / l , -3000 i "$2m Inpact Energy (f t-lb): 51.5 General Yield Load (Pgy)(1b): 2900 3000 i \\ Maximum Load (P **)(1b): 4070 o D 0 1000 2000 -3000 4000.5000 Tyne, psec l -I -[ Specimen No.: 'MA6 1 4000 Test Tenperature (F): +212 p I= pact Energy (f t-lb): 66.5 ]2000 3 General Yield Load (Pgy)(1b): 2720 gogo ( [ Haximum Load (Pmax)(1b): 3730 0 0 1000 2000 3000 4000 5000 l Time, psec t Specimen No.: MD7 4000 Test Te:nperature (F): +300 A Irepact Energy (f t-lb): 89.0 32000 \\ General Yield Load (Pg.)(1b): 2550 1000 Mar.1=ca Load (PDE:)(Ib): 3800 o-0 1000 2000 3000 -4000 5000-Time, psec 1 \\ I

l A-13 t i TABLE A-4. INSTRUMENTED CHARPY IMPACT DATA FOR QUAD CITIES UNIT NO.1 ESW WELD METAL FROM CAPSULE G2 [ i 5000 Specimen No.: MB2 4000 l Test Temperature (F): -100 -3000 Impact Energy (f t-lb): 2.5 32000 I General Yield Load (Pgy)(1by: 1000 Maximu:n Load (Pmax)(1b): 2230 0 0 1000 2000 3000 4000 5000 t I ilme, pec i 5000 Specimen 1:o.: MC5 4000 Test Temperature (F): -60 .3000 Impact Energy (f t-lb): 2.5 2 i 3 000 General Yield Load (Pgy)(1b): 1000ll i o l Maximus Load (Pmax)(ib): 2270 0 1000 2000 3000 4000 5000 i Foe, psec i 5000 Specimen No.: MC6 Test Te:nperature (F): -20 q3000 j2000 f Impact Energy (f t-lb): 30.0 General Yield Load (Pg)(1b): 3270 1000 Maxicum Load (P )(1b): 4000 00 1000 2000 3000 4000 5000 Time, psee i 500'0 Specimen !!o.: MCL 4000 Test Temperature (F): +30 $3000 j2000 Impact Energy (f t-lb): 52.5 General Yield Load (Pgy)(10 : M 1000 Maximum Load (Pnax)(Ib): 3970 0 0 1000 2000 3000 4000 5000 i Time, psec t t h

4-i A-14 TABLE A-4 (Continued) 5000 [ Specinen Ko.: MAC Test Temperatere (F): +55 e 3000 [ Impact Energy (ft-Ib): ,43.5 j2000 2840 1000 General Yield Load (Pg,)(1b): Maximun Load (Pmax)(1b) : 3780 0 ~ 0 1000 2000 3000 4000 500C Time,psec 5000 Specinen No.: MCJ i 4000 Test Temperature (F): +80 e 3000 l/ Impact Energy (f t-lb): 70.0 32000 l General Yield Load (Pg.)(1b): 2800 1000 ( w Maximum Lead (P,g)(1b): 3800 0 0 1000 2000 3000 4000 500C Time,ysec l 5000 Specimen'Eo : MC7 4000 Test Temperature (F): +145 e jm' '3000 g Icpact Energy (f t-lb): 93.0 "3 20M ' General Yic1d Load (Pg7)(1b): 2640 1000 \\ Maximun Load (Pnax)(Ib): 3770 o 0 1000 2000 3000 4000 5000 Time, psee Specimen No.: MCU 5000 4000 Test Terperature (F): +212 e 3000 [ '\\ g Inpact F.ncrgy (It-lb): 97.5 3 2000g General Yield Lead (P h ( 000 -N G Nw-Maximun Lead (PCan)(1b): 3610 o 0 1000 2000 3000 4000 5000 Time, y sec [ D

A-15' i TABLE A-5. INSTRUMENTED CHARPY IMPACT DATA FOR QUAD CITIES IMII NO. 1 ESW HAZ METAL l FROM CAPSULE G1 l 5000 Specimen No.: MKE 4000 Test Temperature (F): -20 $-3000 I Impact Energy (f t-lb): 9.0 $2000 General Yield Load (Pgy)(1b): 3340 1000 Maximum Load (P )(Ib): 3600 0 0 K)00 2000 3000 4000 5000 Time, psec 5000 Specimen No.: MLD gg Tes t Temperature (F): +30 e.3000 Impact Energy (f t-lb): 17.5 }2000 f General Yield Load (Pgy)(1b): 3330 1000 Maximum Load (P )(1b): 4020 0 0 1000 2000 3000 4000 5000 Time, psec 5000 Specimen No.: MK4 4000 Test Temperature (F): +55

• 3000 [

Impact Energy (f t-lb): 29.5 .32000 General Yield Load (PGY)(1b): 3300 1000 Maximum Load (P )(1b): 3920 0 0 1000 2000 3000 4000 5000 Time, psec 5000 Specimen No.: MIA 4000 Test Temperature (F): +80 8.3000 1 Impact Energy (ft-lb): 31.0 32000 General Yield Load (Pgg.)(Ib): 3000 1000 Ma:tinum Load (P )(15): 4000 0 0 1000 2000 3000 4000 5000 I Time, pec I

l A-16 TABLE A-5. (Continued) Specinen No. : ML4 5@ 4000 Test Te: perature (F): +115 ,3000 fg 7 Impact Energy (f t-lb): p0.0 General Yield Load (PGY)(1b): 3180 1000 Maximum Load (Pmax)(1b): 3970 0 - 3000 4000 5000 I 0 1000 2000 Thne, psec I 5000 Specimen No.: MLK 4# j Test Temperature (F): +145 [ 3000 Impact Energy (f t-Ib): 46.5 3 2000 General Yield Load (Pgy)(1b): 3090 000 N Maxinum Load (Pmax)(1b): 4010 o A 0 1000 2000 3000 4000 5000' Tirr.e, psec 5000 Specimen No.: MPE 4000 - 3000 [\\ Test Temperature (F): +212 e T f T Impact Energy (f t-lb): 67.0 3 2000 General Yield Load (PGY ( I 00 ( Maxinua Load (P )(Ib): 3640 0 0 1000 0 3000 4000 5000 Ne, pec 50'00 Specimen No.: MKT 4000 Test Tenperature (F): +300 .3000 /T Iepact Energy (f t-lb): 83.5 32000J L General Yield Load (Pg.)(1b): 2600 1000 Mar.inun Land (P ,)(1b): 3730 0 ~ 0 1000 200 3000 4000 5000 Time, psec

A-17 TABLE A-6. INSTRUMENTED CHARPY IMPACT DATA FOR QUAD CITIES UNIT NO. 1 ESW llAZ METAL FROM CAPSULE G2 5000 Specimen No.: MMC 4000 Test Temperature (F): -100 e Impact Energy (f t-lb): 3.0 3"2000;- General Yield Load (Pg7)(1b): 1000 -Maximum Load (Pmax)(1b): 2180 0' ~ 5000 0 1000 2000 3000 4000 Time, psec 5000 Specimen No.: MM6 4000 Test Temperature (F): -60 [> g j2000 Impact Energy (f t-lb): 31.0 General Yield Load (Pgy)(1b): 3300 1000 Maximum Load (Pmax)(1b): 4300 00 1000 2000 3000 4000 5000 Time,ysac Specimen No.: MHB 5000 Test Temperature (F): -20 4000 3000 Impact Energy (f t-lb): 26.0 m 000 General Yield Load (PGY)(1b): 3090 lo00 Maximum Load (P )(1b): 3920 0 1000 2000 3000 4000 5000 Time, psec Specimen No.: HKA 5000 Test Temperature (F): +30 4000 j [/ j s e 3000 Impact Energy (f t-lb): 119.0 General Yield Load (Pg7)(1b): 2950 32000 Maximum Load (P )(1b): 3980 N l ~ 0 1000 2000 3000 4000 5000 Time, psec

A-18 i TABLE A-6. (Continued) V l 5000 Specimen No.: MM7 00 _m (! \\ Test Temperature (F): +55 e 3000 \\ Impact Energy (f t-lb): 116.0 32000 \\ General Yield Load (Pgy)(Ib): 3000 1000 x Maximum Load (P )(1b): 4000 0 0 1000 2000 3000 00 5000 Time, psec y 5000 Specimen No.: MM5 Test Temperature (F): +80 e,-3000 Impact Energy (f t-lb): 118.5 32000 \\\\ General Yield Load (Pgy)(Ib): 2900 1000 Maximum Load (P m8K 0 1000 2000 3000 5000 Time, psee i 5000 Specimen No.: MKS 4000 .3000 [ Test Tenperature (F): +145 8 Impact Energy (f t-1b): 131.5 j2000 \\ N General Yield Load (PGY}( }* Maximum Load (P,,x)(1b): 3760 0 0 1000 2000 3000 400 5000 Time, psei i 5000 Specimen No.: MMD 4000 Test Temperature (F): +212 e-3000 o s Impact Energy (f t-lb): 127.5 32000 h 2520 1000 \\ General Yield Load (Pgy)(1b): N L Maximun Load (P,)(Ib): 3690 0 0 1000 2000 3000 4000 5000 Time, psec 1 I

A-19 TABLE A-7. INSTRUMENTED CHARPY IMPACT DATA FOR QUAD CITIES UNIT NO. 1 SAW WELD METAL FROM CAPSULE G1 5000 Specimen No.: P1K 4000 Test Temperature (F): -20 8 8 3000 f2000 Impact Energy (ft-Ib): 5.0 General Yield Load (Pgy)(1b): goog Maximum Load (Pmax)(1b): 3420 o e 0 1000 2000 3000 4000 5000 Time, psec 5@ Specimen No.: P2Y 4000 Test Temperature (F): +30 f g Impac Energy (f t-lb): 12.5 "g General Yield Load (Pgy)(ib): 3000 3900 0 Maximum Load (P,,x)(1b.: 0 1000 2000 3000 4000 5000 Time, ps4c t 5000 l I Specimen No.: P4K 4000 f a Test Teraperature (F) +60 ~ 3000 $2000 Impact Energy (It-lb): 20.5 3200 1000 General Yield Load (Pg,)(Ib) : tiaximum Load (Pmax)(1b): 3830 0 1000 2000 3000 4000 5000 73,,,p3,g 5000 l Specitnen No.: P3T 4000 8 Test Temperature (F): +145 3000 32m l-Impact Energy (f t-Ib): 34.5 General Yield Load (PGY} ( } 0 !!aximum Load (Pmax)(ib): 3900 0 1000 2000 3000 4000 5000 i Time, pset i ~ e-

l A-20 TABLE A-7. (Continued) 5000 Specinen No. : P36 8 3000 [ Test Temperature (F): +212 Inpact Energy (ft-lb): ,44.0 }2000 \\ General Yield Load (PGY)(1b): 3000 t000 3N Jiaximum Load (P )(1b): 3780 0 0 1000 2000 3000 4000 5000 Time, psec 5000 Specinen Ea.: P15 Test Temper.ature (F): +300 e 0% Impact Energy (f t-lb): 46.0 j2000 \\ 2800 1000 General Yield Load (PgY)(Ib): s g linximun Load (P, )(1b): 3510 0 0 1000 2000 3000 4000 5000 Tune, pset 5000 Specinen Ko.: P3K 4000 Test Temperature (F): +300 p ~ 3000 1 1= pact Energy (f t-lb): 36.0 I ~ ( General Yield Load (Pg7)(Ib): 3120 1000 Maximum Load (Pnax)(1b) : 3600 0 0 1000 2000 3000 4000 5000 Time, psee t Speci=en No.: P22 5000 Test Temperature (F): +350 4000 e h 3000 Impact Energy (f t-lb): 52.0 i \\ General Yield Load (PGY)(1b): 2810 h 1000 Mar.imun Load (P )(1b): 3540 l 0 0 1000 2000 3000,4000 5000 Time, pse: i b L

m i 'l i A-21 i l TABLE A-8. INSTRUMENTED CHARPY IMPACT DATA FD'l QUAD CITIES UNIT NO, 1 SAW HAZ METAL FROM CAPSULE G1 5000 Specimen No.: P7B Test Temperature (F): -20 2 3000 f ]2000 Impact Energy (f t-lb): 12.5 General Yield Load (Pgy)(1b): 1000 l Maximum Load (P )(1b): 4000 00 1000 2000 3000 4000 5000 Time, psec + ? I cA00 Specimen No.: P6Y 4000 l Test Temperature (F): +30 e.3000 32000l = Impact Energy (f t-lb): 35.0 l General Yield Load (Pgy)(1b): 3400 1000 Maximum Load (P )(1b): 4230 0 0 1000 2000 3000 4000 5000 Time, psec t 5000 Specimen No.: PAM 4000 Test Temperature (F): +80 e.3000 }2000-Impact E. 3f (f t-lb): 35.0 General Yield Load (Pgy)(1b): 3360 1000 Maximum Load (P )(1b): 3900 00 1000 2000 3000 4000 5000 Time, psec j l 5000 i Specinen No.: P63 4000 i Test Temperature (F): +125 a 3000 Impact Energy (ft-lb): 48.0 32000 I -( General Yield Load (PO,)(1b): 3200 1000 3 N i Maxitsm Load (P )(1b): 3910 0 1000 Moo 3000 4000 5000 0 Time, psec i i i P .h I b

I t A-22 i TABLE A-8. (Continued) I i 5000 l Specimen No.: P6Y 4000 Test Temperature (F): +145 n " 3000 f \\.. Impact Energy (ft-Ib): 70.5 General Yield Load (Pg7)(1b): 1000 -- \\ 3110 b_c._ Maximum Load (Pmax)(1b): 3890 o 0 1000 2000 3000 4000 5000 Time, psec i i Specimen No.: PAB 5000 4000 t Test Temperature (F): +212 , _ 000 + 3 \\ I Impact Energy (f t-lb): 55.0 = 3 2000 General Yield Load (Pgy)(1b): 3220 Maximu:n Load (Pmax)(1b): 3980 0 0 10 0' 0 2000 3000 4000 5000 Time, pec j 5000 Specimen No.: PAU 4000 j f-3000^\\ Test Temperature (F): +300 I s Impact Energy (f t-lb): 65.5 ' 2000 g General Yield Load (P N CY 0 Maximum Load (Pmax)(1b): 3570 0 1000 2000 3000 4000 5000 i Time, psec .} i

5000, j

Specimen No.: P7A 403o j f ^ Test Temperature (F): +350 . 3000 l 7 Impac t Energy (f t-Ib): 59.0 3 2000 l \\ 1000 General Yic1d Load (Pg.)(1b): 2800 l 0 ~~ Maximum Load (P""*)(1b): 3460 0 .1000 2000 "3000 4000 5000 i Time, psee n

A-23 1 Fracture Load-displacement Raw Remarks type curves data I m P Brittle fracture c 3 F 3 i Defteetion t II 15 I P Brittle fracture c; e GY 1 t I Deflection l ) P Britt.le fracture followed by III g7 a fracture indicative. of shear lip formation De flection Stable crack propagation IV t P followed by' unstable brittle p CY' fracture and' fracture P max indicative of shear lip formation ~ De fl e ct i on V 1l P Stable crack propagation gy' j followed by fracture p max indicative of shear lip Deflection ? VI = P Stable crack propagation 5 6' followed by. gross deformation p max Deflection l e t FIGUPI A-4 THE SIX TYPES OF FRACTURE FOR UOTCHED BAR BENDING j l i

A-24 I t The pertinent data used in the analysis of each record are the general yield load (Pgy), maximun load (P ), and fracture load (P ), The impact [ p energy values listed in the tables are those norcally obtained from the impact machine dial. These values are in excellent agreement with energy values from the area under the load-time curves. f The Charpy energy curves and the load-te=perature information I obtained from the instrumented Charpy tests are shown in Figures A-5 through -f A-12. These figures illustrate a unique feature of this type of analysis; that is, the determination of "a definitive fracture transition temperature by discrimination between fractures occurring below and above general yield I (PGY). This transit' ion is a clear indication of the mechanical properties of the material and does not depend on empirical correlations, as the nil-l ductility transition tecperature determined by the 30 f t-lb fix temperature does. In general, the curves show both the general yield load and the maximum load initially increasing as temperature is decreased from the upper [ shelf region of the Charpy impact curve. As temperature is further decreased through the transition temperature region, the maximum load goes through a f maximum and drops off as teeperature continues to be decreased. The general i yield load is also quite sensitive with respect to temperature. As the temperature is decreased from the upper shelf region, the general yield load f increases substantially. -{ f CONCLUSIONS The instru=ented Charpy impact test technique was used to study the f impact behavior of pressure-vessel, materials. The maximum load was shown to go through a raaximum as temperature is lowered f rom the upper shelf region [ into the transition temperature region. In addition, the general yield load i was shown to increase as temperature is decreased. p t l

f - i A-25 i 'i t I I t 4500 n O l Pnax 4000-. O O ',i O P.1 { 3500 i 6 .l J o a i e .3 3000-- O-P GY b. t 2500-- - - 150 2000-- f - 125 l 'f -- 100 D 3' O -75 x. -i i = l be t O t - -50 [ - t; O O -25 l O D/ i - ?b O I -100 0 100 200 300 { Temperature, F l l t p FIGURE A-5. INSTRUMENIED CHARPY LOAD-TEMPERATURE AND EhTRGY-TEMPERATURE CORVES FOR QUAD CITIES UNIT NO 1 BASE METAL FROM CAPSULE G1 { i l

~- h A-26 4500 O 4000-- P max O O + i , 3500-- g m' E" 3000-- P CY 250&- O 6 g -- 150 2000-- i J 125-oo e 1 -- 100 U O D# / -- 75 Dw D E' --50 g/ -- 25 i D i O i -100 0-100 200 ,300 k Temperature, F l 4 FIGURE A-6. INSTRUMENTED CHARPY LOAD-TEMPERATURE AND ENERGY-TEMPERATURE CURVES FOR QUAD CITIES UNIT NO.1 PASE METAL FROM CAPSULE G2 t k t i m

A-27 4500 O' N r,,, O t 3500-- t

3 i

i, t 2 300&- o I a P o g7 2504-O o O -150 200V +-! - 125 t - -100. $ a 0 --75 O y u -50 D i'; O I 25 O oso i 0 -100 0 100 200 300-Temperature, F l 71GURE A-7. INSTRUMENTED CHARPY LOAD-TEMPERATURE AND DiERGY-TEMPERATURE CURVES FOR QUAD CITIES UNIT NO. 1 ESW WELD METAL FROM CAP

l s A-28 1 -t 4500 i 4006 AO P O O 3500-- - g ? i d %,o i i Oa 3000-- A D \\ 3 Pgy \\ O 2504 O O -- 150 2000-- I -125 t -- 100 .o O F T aW --75 ~x i ec u --50 g I O -25 O O 0 -lb0 100 2b0 300 Temperature, F. t e INSTRUMENTED CHARFY LOAD-TEMPERATURE AND ENERGY-TEMPE FIGURE A-8. I FOR QUAD CITIES UNIT NO. 1 ESW WELD METAL FROM CAPSULi t 3 i

W I A-29 4500 O 4000-- 'O Pmax O O 9 3500- - ONko l' o O 3 3000-P o GY a 2504 - i 6 -- 150 2000- -- 125 -- 100 g O e 75 O b O g-O --50 5 --25 O O O -100 0 100 200 300 Temperature, F P W FIGURE A-9. INSTRL&iENTED CHARPY LOAD-TEMPERATURE AND ENERGY-TEMPERATURE CURVES FOR QUAD CITIES UNIT NO. 1 ESW HAZ METAL FROM CAPSULE C1

A. 4500 0 4000-- O O g max , 3500-- S g .o .s 3 -E 8" 300&- o GY 2500-- O O - - 150 2000-- O O - 125 e O O,0 l --.100 g l [ i --75 t --50 5 0 -25 l O i 0 -100 0 100 200 300 'l Temperature, F ' FIGURE A-10. INSTRUMENTED Ci!ARPY LO4D-TEMPEPATURE AND ENERGY-TEMPERATURE CURVES FOR QUAD CITIES UNIT NO.1 -ESW HAZ METAL FROM CAPSULE G2 l i 4

A-31 'f 4500 i

.l i

4000-- I 0% P max

b 3500--

O O .5 O i O P GY a i o 4 3000-- { 2500-- I -- 150 2000-- -- 125 d -i --100 2 u. + --75 .b .e tal pg#U -50 0 --25 / as- ~ I O l 0 -100 0. 100 200 300 350 i Temperature, F l I i l FIGURE A-11. INSTRUMENTED CHARPY LOAD-TEMPERATURE AIG ENERGY-TEMPERATURE i CURVES FOR QUAD CITIES UNIT NO. 1 SAM WELD METAL FROM CAPSULE G1 1 t-i

i A-32 i 4500 O i O 4000-- O Og x i C 3500-- oa I o O.y .~ a CY l g g 1 e 3 3000-- L, t 2500-- 7 --150 { 2000-- ,--125 l .o --100 - y i --75 g g U. [j+ O --50 l 0 t O O --25. O f 0

.106

.0 100 200 300' [ Temperature, F INSTRUMENTED CHARFY LOAD-TEMPERATURE AND ENERCY-TEMPERATURE FIGU2E A-12. CURVES FOR QUAD CITIES UNIT NO.1 SAW IIAZ METAL FROM CAPSi e i 17 t' m s t r c w +

m _,1 l A-33 - i i APPENDIX B REFERENCES (1) Wu11aert, R. A., Ireland, D. R., and Tetelman, A. S., " Radiation i Ef fects on the Metallurgical Fracture Parameters and Fracture j Toughness of Pressure Vessel Steels", paper presented at the ASIM i Annual Meeting, Niagara Falls, New York, June 29, 1970. I (2) Wu11aert, R. A., ". Applications of the Instrumented Charpy Impact Test", in Impact Testinn of Metals, American Society for Testing and Materials Special Technical Publication 466, p 148 (1970). (3) Perrin, J. S. and Sheckherd, J. W., " Current and Advanced Pressure Vessel Surveillance Specimen Evaluation Techniques", Proceedings of i 21st Conference on Remote Systems Technology, American Nuclear i Society (1973). i (4) Wilshaw, T. R., and Pratt, P. O., "The Effect of Temperature and Strain Rate on the De, formation and Fracture of Mild-Steel Charpy 1 Specimens", in Proceedings of the First International Conference on 3 Fracture, Sendai, Japan, September,1965, 2, p 973. j\\ (5) Tetelman, A. S., and McEvily, A. J. R., Fracture of Structural Materials i John Wiley and Sons, Inc., New York (1967). i (6) Knott, J. F., "Some Effects of Hydrostatic Tension on the Fracture Behavior of Hild Steel", Ph.D. dissertation, University of Cambridge, l Cambridge, England (1962). (7) Fearnehough, G. D., and Hoy, C. J., " Mechanism of Deformation and I Fracture in the Charpy Test as Revealed by Dynamic Recording of Impact Loads", Iron Steel Inst., 202, 912 (1964). 5 (8) Server, W. L., and Tetelman, A. S., "The Use of Precracked Charpy - f Specimens to Determine Dynamic Fracture Toughness", UCLA-ENG-7153 j (July, 1971). i i N i i I i i - a}}