ML20062J407

Reactor Pressure Vessel Surveillance Program:Capsule Basket 12 & Capsule Basket 13

ML20062J407
Person / Time
Site:	Dresden, Quad Cities
Issue date:	09/19/1975
From:	Farmelo D, Perrin J, Wooton R COMMONWEALTH EDISON CO.
To:
Shared Package
ML17179B166	List: ML17179B165 ML20062J404 ML20062J407 ML20062J410
References
NUDOCS 9311040373
Download: ML20062J407 (100)

Text

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FINAL REPORT

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QUAD CITIES NUCLEAR PLANT UNIT NO. 2 REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM: CAPSULE EASKET NO.12 AND CAPSULE BASKET NO. 13 r

to CO>DichWEALTH EDISON COMPAhT by i

J. S. Perrin, D. R. Fartnelo R. O. Wooton, L. M. Lowry, and E. O. Fronn September 19, 1975 EATTELLE Columbus Laboratories 505 King Avenue Columbus, Ohio 43201 9311040373 931022 K

DR ADOCK 05000237 !!

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l TABLE OF CONTENTS l

Page i

i LIST OF FICURES.

11 s

.iv i

LIST OF TABLES...

.i

SUMMARY

.....1 F

.i INIRODUCTION.

2

,t CAPSULE RECOVERY AND DISASSEMBLY...............

4 SPECIMEN PREPARATION.

.....,... 10 i

EXPERIMENTAL PROCEDURES.

12 Neutron Dosimetry..

12 t

-1 Charpy Impact Properties....

.14 i

Hardness Properties.

16

- j Tensile Properties.

17 RESULTS AND DISCUSSION..

19 Neutron Dosimetry.

19 i

i Charpy Impact Properties.

26

.i i

'I liardness Properties.

......47 q

e Tensile Properties.

50 1

CONCLUSIONS.

.-.57 REFERENCES.

58 i

APPENDIX A INSTauMENTED CHARPY EXAMINATION.

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LIST OF FIGURES Page FIGURE 1A.

QUAD CITIES UNIT NO. 2 CAPSULE BASKET ASSDiBLY No.12 5A FIGURE 13 TOP VIEW OF QUAD CITIES UNIT NO. 2 NEAR-WALL CAPSULE LASKET ASSDIBLY NO. 13..........

5B FIGURE 1C.

SIDE VIEW OF QUAD CITIES UNIT NO. 2 NEAR-WALL CAPSULE BASKET ASSD4BLY NO. 13..........

5B FIGURE 2.

TYPICAL CHARPY CAPSULE WITH CHARPY SPECDIEN.

.7 FIGURE 3.

TYPICAL TENSILE CAPSULE WITH TENSILE SPECDIEN...

.7 FIGURE 4 CHARPY V-NOICH IMPACT SPECD'EN.

11 FIGURE 5.

TENSILE SPECDIEN.

.. 11 FIGURE 6.

INSTRUMENTED CHARPY MACHINE..

15 FIGURE 7.

EXTENSOMETER EXTENS1.N ARMS AND SIRAIN CAGE ASSDIBLY USED FOR TEhSILE TESTING.

. 18 FIGURE 8.

CALCULATED NEUIRON FLUX SPECTRUM AT 35' NEAR-WALL CAPSULE EASKET ASSD1BLY LOCATION.

. 24 FIGURE 9.

CALCULATED NEUIRON FLUX SPECTRUM AT NEAR CORE TOP GUIDE CAPSULE LASKET ASSDiBLY.

. 25 FIGURE 10. CHARPY D1 PACT FROPERTIES VERSUS TDIPERATURE FOR QUAD CITIES UNIT NO. 2 EASE METAL..

. 31 FIGURE 11, CHARPY IMPACT PROPETIES VERSUS TDIPEFATURE FOR QUAD CITIES UNIT NO. 2 ESW WELD METAL,

. 32 FIGURE 12. CHARPY IMPACT PROPERTIES VERSUS TDIPERATURE FOR QUAD CITIES UNIT No. 2 ESW RAI METAL.

. 33 FIGURE 13. CHARPY DiPACT PROPERTIES VERSUS TDIPERATURE FOR QUAD CITIES UNIT NO 2 SAW WELD METAL,

34 FIGURE 14. CHARPY DiPACT PROPERTIES VERSUS TDIPERATURE FOR QUAD CITIES UNIT NO. 2 SAW IIAZ METAL...

35 FIGURE 15. CHARPY DIPACT SPECDIEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 2 IRRADIATED PASE MEIAL FR0td CAPSULE G2......................

. 36 FIGURE 16. CIRRPY IMPACT SPECDIEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO 2 IRRADIATED PASE METAL FRG1 CAPSULE G1.

................. 36 FIGURE 17. CHARPY D1 PACT SPECIMEN FRACTURE SLTJACES FOR QUAD CITIES UNIT NO. 2 IRRADIATED ESW WELD METAL FROM CAPSULE G2.....

. 37

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LIST OF PIGURES (Continued) i i

FIGURE 18. CHARPY D1 PACT SPECII1EN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 2 IRRADIATED ESW WELD METAL FROM CAPSULE G1,.

37 FIGURE 19. CIMRPY D1 PACT SPECDIEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 2 IRRADIATED ESW HAZ METAL FROM CAPSULE G2.....

. 38 FIGURE 20. CIMRPY MPACT SPECEEN FRACIURE SURFACES FOR QUAD CITIES UNIT NO. 2 IRRADIATED ESU HAZ 9'

METAL FROM CAPSULE G1..............

38 FIGURE 21. CHARPY DIPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 2 IRRADIATED SAN WELD METAL FROM CAPSULE G1..............

39 FIGURE 22. CHARPY EPACT SPECEEN FRACTURE SURFACES FOR i

QUAD CITIES UNIT NO. 2 IRRADIATED SAN IMZ METAL FR0t1 CAPSULE G1.

. 39 FIGURE 23. THE EFFECT OF IRRADIATION ON VARIOUS HEATS 0F A302B/A533B 44 FIGURE 24. COMPARISON OF 30 FT-LB TRANSITION TD:PERATURE VALUES FROM VARIOUS SURVEILLANCE PROGRAMS FOR A302 GRADE B PRESSURE VESSEL STEEL.

45 FIGURE 25. COMPARISON OF 50 FT-LB TRANSITION TEIPERATURE SHIFT VALUES FROM VARIOUS SURVEILLANCE PROGRAMS FOR SA302 GRADE B PRESSURE VESSEL MATERIALS.

. 46 FIGURE 26. POSTIEST PHOTOGRAPHS OF QUAD CITIES CIIT NO. 2 Tn:SILE SPECmENS.

. 52 FIGURE 27. POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT No. 2 IRRADIATED TENSILE SPECDIENS.

. 53 FIGURE 28. POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 2 IRRADIATED TENSILE SPECEES.

. 54 FIGURE 29. POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 2 IRRADIATED TENSILE SPECDIENS..

. 55 3

FIGURE 30. TYPICAL STRESS-STRAIN CURVE..

. 56 l

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'L LIST OF TABLES j

'f Page TABLE 1.

INVENTORY OF SPECDIENS RD10VED FRO)1 CHARPY AND TENSILE CAPSULES FRO)1 CAPSULE BASRET I

ASSDiBLY NO.12 FRa1 QUAD CITIES UNIT NO. 2....

8 TABLE 2.

INVENTORY OF SPECD1 ENS RD10VED FRQi CHARPY AND h

TENSILE CAPSULES FR@l CAPSULE BASRET ASSDiBLY NO. 13 FROM QUAD CITIES UNIT No. 2.... _....

9 TABLE 3.

CALIBRATION DATA FOR THE BCL HOT LABORATORY CHARPY DiPACT MACHINE..

.14 TABLE 4 QUAD CITIES UNIT NO. 2 FAST NEUTRON DOSHIETRY RESULTS..

.20 TABLE SA. VALUES USED IN QUAD CITIES UNIT NO. 2 DOSHIETRY CALCULATIONS.

.23 TABLE SB. ACTIVATION CROSS SECTION IN BARNS FOR QUAD CITIES UNIT NO. 2....

.23

{

TABLE 6.

Cl%RPY V-NOTCH 'DiPACT RESULTS FOR QUAD CITIES UNIT No. 2 EASE METAL SPECIMENS FRai CAPSULE G2.. '.27 TABLE 7.

CIMRPY V-N07CH DIFACT RESUL7S FOR QUAD CITIES UNIT No. 2 BASE METAL SPECDIENS FRG1 CAPSULE G1..

27 TABLE 8.

CHARPY V-NOICH DIPACT RESUL75 FOR QUAD CITIES UNIT No. 2 ESU WELD METAL SPECD1 ENS Frei CAPSULE G2 28 l

't TABLE 9.

CIMRPY V-NOTCH D1 PACT RESULTS FOR QUAD CITIES 28 UNIT NO. 2 ESW UELD METAL SPICDiENS FR031 CAPSULE G1.

28 TABLE 10. CHARPY V-NOICH DiPACT RESULTS FOR QUAD CITIES UNIT NO. 2 ESWWIRZ HETAL SPECDIDiS l

FRe1 CAPSULE G2 29 TABLE 11. CllARPY V-NOTCH DIPACT RESULTS FOR QUAD CITIES UNIT NO. 2 ESU HAZ METAL SPD'DIENS FR&1 CASSULE G1.................

.29 j

l TABLE 12. CIMRPY V-NOTCH D1 PACT RESULTS FOR QUAD CITIES j

UNIT NO. 2 ' SAW UELD METAL SPECDIENS FROM CAPSULE Gl..........

30 I

TABLE 13. CinRPY V-NOICH DIPACT RESULTS FOR QUAD CITIES j

UNIT NO. 2 SAW IRZ METAL SPECIMD;S

?

FROM CAPSULE G1..

.30 TABLE 14. Cl%RPY D1 PACT PROPERTIES FOR QUAD CITIES UNIT NO.

j UNIT No. 2..

. 41 1

TABLE 15. 30 FT-LB AND 50 FT-LB TRANSITION TDiPERATURE

.)

SHIFTS DUE TO IRRADIATION FOR QUAD CITIES UNIT NO 2 NEAR-CORE CAPSULE C1.....

42 I

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iv LIST OF TABLES Pace TABLE 1.

INVENTORY OF SPECDIENS REMOVED FROM CHARPY AND TENSILE CAPSULES FROM CAPSULE BASKET ASSEMBLY NO.12 FRm QUAD CITIES UNIT NO. 2....

8 i

TABLE 2.

INVENIORY OF SPECIMENS REMOVED FROM CHARPY AND TENSILE CAPSULES FROM CAPSULE BASKET ASSDiBLY r

No. 13 FROM QUAD CITIES UNIT NO. 2........

9 TABLE 3.

CALIBRATION DATA FOR THE BCL HOT LABORATORY CHARPY IMPACT MACHINE...............

14 TABLE 4 QUAD CITIES UNIT NO. 2 FAST NEUIRON DOSDIETRY RESULTS................. 2 0 TABLE 5A. VALUES USED IN QUAD CITIES UNIT NO. 2 DOSDiEIRY CAIEULATIONS.

23 TABLE SB. ACTIVATION CROSS SECTION IN BARNS FOR QUAD CITIES UNIT NO. 2 23 TABLE 6.

CHARPY V-NOICH IMPACT RESULTS FOR QUAD CITIES UNIT NO. 2 BASE METAL SPICIMENS FROM CAPSULE G2..

27 TABLE 7.

CHARPY V-NOICH IMPACT RESULTS FOR QUAD CITIES UNIT NO. 2 BASE METAL SPECIMENS FROM CAPSULE G1.. 27 TABLE 8.

CHARPY V-NOICH IMPACT RESULTS FOR QUAD CITIES UNIT NO. 2 ESW WELD METAL SPIEDIEN3 FRai CAPSULE G2

............. 28 TABLE 9.

CHARPY V-NOICH DiPACT RESUI,TS FOR QUAD CITIES 28 UNIT NO. 2 ESW WELD METAL SPII:DiENS FROM CAPSULE G1.................... 28 TABLE 10. CHARPY V-NOICH D1 PACT RESULTS FOR QUAD CITIES UNIT NO 2 ESW HAZ METAL SPECDIDiS FRQ4 CAPSULE G2

........29 TABLE 11. CHARPY V-NOICH IMPACT RESULTS FOR QUAD CITIES UNIT NO. 2 ESW HAZ METAL SPII DIENS FROM CAPSULE Gl.

.............29 TABLE 12. CHARPY V-NOICH DiPACT RESULTS FOR QUAD CITIIS UNIT NO. 2 SAW WELD METAL SPECDiENS FROM CAPSULE Gl.................. 30 TABLE 13. CHARPY V-NOICH DiPACT RESULTS FOR QUAD CITIES UNIT NO. '2 SAW HAZ METAL SPECDIDsS FROM CAPSULE G1.................. 3 0 TABLE 14. CHARPY DiPACT PROPERTIES FOR QUAD CITIES UNIT NO.

UNIT NO. 2

................... 41 TABLE 15. 30 FT-LB AND 50 FT-LB IRANSITION TDiPERATURE SHIFIS DUE TO IRRADIATION FOR QUAD CITIES i

UNIT NO. 2 NEAR-CORE CAPSULE Gl.......... 42

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1,IST OF " ABLES (Continued) j P

I TAELE 16. EARDNESS PROPERTIES OF QUAD CITIES UNIT NO. 2 i

IRRADIATED SPECDIDeS.

.48 i

TABLE 17. CO'1PARISON OF UNIRRADIATED AND IRRADIATED AVEPdGE i

HARDNESS RESULTS FOR QUAD CITIES UNIT NO. 2 SPECDiENS.

49 TABLE 18. TD4SILE PROPERTIES OF QUAD CITIES UNIT NO. 2 f

IRRADIATED SPECIMENS -

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FINAL REPORT A

on

~ i QUAD CITIES NUCLEAR PLAITI UNIT No. 2 REACTOR FRESSURE VESSEL SURVEILLANCE PROGRAM: CAPSULE EASKET NO. 12 AND CAPSULE BASKET NO. 13 j

to i

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COMMONWEALTH EDISON CG1PAhY t

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r by J. S. Perrin, D. R. Farmelo R. O. Mooton, L. M. Lowry, and E. O. Fromm l

September 19, 1975 I

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BATTELLE Columbus Laboratories

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505 King Avenue l

Columbus, Ohio 43201' 2

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i INTRODUCTION i

Irradiation of materials such as the pressure vessel stects used in reactors causes changes in tne mechanical properties, including tensile, impact, and fracture toughness.(1-7) Tensile properties generally show a t

decrease of both uniform elongation and reduction in area accompanied by

{

an increase in yield strength and ultimate tensile strength with increasing l

neutron exposure. The impact properties as determined by the Charpy'V-notch impact test generally show a substantial increase in the ductile to brittle transition temperature and a drop in the upper shelf energy.

l Commercial nuclear power reactors are put into operation with j

reactor pressure vessel surveillance programs. The purpose of the surveillance i

program associated with a reactor is to monitor the charges in mechanical properties as a function of neutron exposure. The surveillance program I

i includes a determination of both the preirradiation base line mechanical properties and periodic determinations of the irradiated mechanical properties. The materials included in a surveillance progrms are base metal, weld metal, and heat-affected-zone (IBZ) metal from the actual components t

used in' fabricating the vessel.

The irradiated mechanical properties are determined periodically by *csting specimens from surveillance capsulcs. These capsules typically

'j contain neutron flux monitors, Charpy impact specimens, and tensile specimens.

Capsules are located between the inner wall of the pressure vessel and the reactor core, so the specimens receive an accelerated neutron exposure.

Capsules are periodically removed, and sent to a hot laboratory for disassembly and specimen evaluation.

Quad Cities Unit No. 2 has a surveillance program. ' This is I) described in a report issued by General Electric

, and is based on

-l E185 " Surveillance Tests on Structural Materials in Nuclear Reactors".( )

f ASTM a

At the tbme of initial operation of the recctor, the pressure-temperature operating curves were specified. During the life of the reactor, the curves-i 4

i l

(1) References at end of text.

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are to be revised to account for the increases in the transitien temperatures of the vessel materials.. Both the 30 ft-lb and 50 ft-lb transition temperatures are presented in the present report.

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

These 1

materials include base metal, submerged-arc-veld (SAW) weld metal, SAW InZ -

metal, electro-slag-weld (ESW)wpid metal, and ESW IIAZ metal. The present report describes the results obtained from examination of the.two capsule basket assemblies removed from the reactor.

In addition to the normal information obtained during a Charpy

- r impact test, additional information was determined using an instrumented Charpy impact machine.

The additional information is reported in Appendix A -

of this report.

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CAPSULE RECOVERY AND DISASSDfBLY e

The transfer of the two capsule basket assemblies from the vessel to the spent fuel pool was handled by reactor personnel. After I

transfer, they then sectioned one assembly in the spent f uel pool using an H. K. Porter hydraulic cutting tool. The other assembly was not cut 3i because it was small enough to fit into the cask without cutting. 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 two assemblies were individually loaded into the cask. This consisted of-hooking onto the samples with a piece of nylon rope with a hook attached-i and transferring them from the pool into the cask by crane. The cask lid was installed, bolted in place, and the exterior surface of the cask was decontaminated by reactor personnel. After decontamination, the cask i

surf ace was below the max,inum allowable shipping limits of 2200 t

2 2

disintegrationr/100 cm / min Sy and 220 disintegrations /100 cm / min n.

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

}

Upon arrival at BCL, the assemblies were removed from the cask and transferred to a hot cell for visual examination and disassembly.

Figure 1A shows Capsule Basket Assembly No.12 (Capsule G1).. Visual examination revealed no unusual features or damage.. Capsule Basket Assembly l

No.12 had the. identification "117C3732G-1".

Figures 1B and IC show top and side views of Capsule Basket Assembly No.13 (Capsule G2). Visual examination revealed the assembly was slightly warped, as can be seen in Figure IC.

This figure also shows j

that the lef t hanger attachment is pulled away from the main body of the l

assembly. This damage may have occurred at the reactor when the assemblies were being prepared for shipment. Subsequent examination of specimens revealed no apparent dmnage to specimens. Capsule Basket Assembly No.13 had identification number "117C3732G-2".

j The two capsule basket assemblics were cut apart using a flexible abrasive wheel attached to a Mototool. Capsule Basket Assembly No.12 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 rom the identification number end of the capsule basket assembly.

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FIGURE 1A.

QUAD CITIES UNIT NO 2 CAPSULE i

BASKET ASSEMBLY NO.12 4

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FIGURE IB.

TOP VIW OF QUAD CITIES UNIT NO. 2 NEAR-WALL j

CAPSULE BASKET ASSEMBLY NO. 13 l

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SIDE VIN OF QUAD CITIES UNIT NO. 2 NEAR-RALL l

CAPSULE BASKET ASSEMBLY NO. 13 Photograph shows slight varp of the capsule s

basket assembly, a

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Tensile capsule G6 Tensile capsule G7 Tensile capsule GS j

Tensile capsule'G9 Tensile. capsule G10 Charpy capsule 117C3570G10 i

Charpy capsule 117C3570G11 Charpy capsule 117C3570G12

{'

Charpy capsule 117C3570G13 I

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

Capsule Basket Assembly No. 13 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.

Tensile capsule C6 Tensile capsule G8 Tensile capsule G10 Charpy capsule 117C3570G10 Charpy capsule 117C3570G11 Each of the two Charpy capsules contained an iron, e nickel, and a copper dosimeter wire.

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

Figure 3 shows a typical tensile capsule with a single tensile specimen. Charpy capsules contain up to 12 -

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

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.12 and in Table 2 for capsule basket assembly No. 13.I")'

(a) In later sections of this report Capsule Basket' Assembly No. 12 and Capsule Basket Assembly No. 13 are referred to as

" Capsule G1" and " Capsule C2", respectively.

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FIGURE 2.

TYPICAL CHARPY CAPSULE WITH CHARFY SPECIFR I

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FIGURE 3.

TYPICAL TDiSILE CAPSULE WITH TDiSILE SPECIMD4 i

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TABLE 1.

INVDITORY OF SPECDIENS RD10VED FROM CHARFY AND TD SILE CAPSULES FRO 31 CAPSULE EASKET ASSD1BLY NO.12' FRG4 QUAD CITIES UNIT NO. 2.

t Charpy Capsule G10 Gil G12 G13 T47 EE U7P TLT

.i T3K T7A U4M UA1 T43 T65 U4L UCD

'i T25 T62 U4K UCA T4M D1T U6G UAM T2M DIY U3U i

T4.A T7C U4A T3C D14 U4P j

T61 30 U4C i

T6A DID U6B 1

1 T6T D16 U6K i

TBJ D17 U3D f

f Tensile Capsule C6 G7 G8 G9 G10 UD3 UP1 UJJ UU1 ULC I

UD5 UPD UJT UUC ULB 1

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INVD4 TORY OF SPECI'1 dis RD10VED FROLI

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CHARPY AND TENSILE CAPSULES FROM -

CAPSULE EASKET ASSDIBLY No.13

'i FROM QUAD CITIES. UNIT NO.'2 i

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Charpy Capsule t

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G10 Gil

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T3B DIK T4Y D1J T4C dip T4J D &!

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TB2 TAJ T64 TAM

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C6 GB G10 UL2("}

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(a) Specimen identification obliterated during j

removal from capsule; identification was

~ inferred from inventory list supplied by.

Co:monwealth Edison.

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SPECIMEN FREPARATION 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 slabs taken parallel to the plate surfaces and at the 1/4 plate thickness. Base metal Charpy and tensile specimens were machined with their longitudinal axes parallel to the plate rolling direction.. Charpy

}

t specimen 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 i

axis of the notch is perpendicular to the plate surface.

The notch radius

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t is at the intersection of the base metal and the veld metal.

The Charpy impact specimen design is shown in Figure 4.

It is the standard specimen design recommended in AS*D1 Standard E23-72 The tensile specimen design is shown in Figure 5.

It has a nominal 0.250 in.

gage diameter and a nominal 1.00 in. gage length.

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FIGURE 4 CHARPY V-NOTCH IMPACT SPECIMEN

.4375 - 14 UNC ~24-f I

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/g,gg y,/CN,PU,*/CH HT PR BOIH ENDS GAGE LEt/GTH gg tDS t.02

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3.00 NOTES 4. 0 01 D:A. AT CENTER OF REQUCED SECTION. D's ACTUAL D DIA +.002

1. D:.250 TO.005 ATENDS OF REDUCEO SECTION TAPERING TO D AT CENTER.

2. GR///D REDUCED SECTION a RAOli TO 32/RADH TO BE tat / gel /T TO REOUCED SECTION IYITH f.'O CIRCULAR TOOL MARKS AT POINT Of TANGENCY OR WITHIN REOUCED SECTIOrl. Pott /TOF TANGENCY SHALL NOTLIE WITHIt/ RECUCED SECTION.

FIGURE 5.

TENSILE SPECIMDJ

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l EXPERD1 ENTAL PROCEDURES f

This section describes the procedures used in the determination of neutron exposure and the impact, hardness, and tensile properties. All testing and evaluations were performed at Batte11e's Columbus Laboratories.

Original data is recorded in BCL Laboratory Record Books 31230 and 31684

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Neutron Dosimetrv Neutron dosimeter wires were located in the neutron dosimeter 5

monitor capsule and in each of the two capsule basket assemblies. Each

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l Charpy capsule in the two capsule basket assemblies contained one iron,.one copper, and one Ni-Co wire.

In accordance with General Electric recommendations, the nickel wires were not counted because of the short j

58 58 half life associated with the g

g Co reaction. The reactions and the associated AS'IM standards are as follows-(

}

Material Reaction AS*IN Standard

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f 1ron Fe (n, p) Mn E263-70 63 Copper Cu (n, 0) OCo E523-74 i

i Af ter removal from their containers, the wires were identified, placed into individual vials, and transferred to the radiochemistry laboratory. They 1

were then cleaned by wiping using successive swabs containing dilute nitric acid, distilled water and reagent acetone until residual contamination was completely removed. Weights were obtained to 0.0001 g on a calibrated analvtical balance. The wires were then mounted for counting by gamma ray

?

spectrometry.

The activation products were analyzed by gamma ray spectrometry l

usin;; a 3 in, diam x 3 in. long AaI (TI) scintillation crystal detector and a 400 channel analyzer capable of 7.0 percent resolution FWIM (full width half maximum) at the 0.662'MeV' Cs-

"Ba gn=ma ray energy level, u

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I The analyzer was calibrated with standard reference materials obtained j

f rom the National Bureau of Standards. To calculate neutron flur. from j

the dosimeter gamma activities at tbne of removal from the reactor, a knowledge of the reactor history and exact location of the samples was j

required as shown in the following equation:'

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= Nc0[1 - exp(-At )] or d a gggy,,xp(_gg ))

g l

I

.3 where

-2

-1 i

c = neutron flux in cm -see I = disintegrations per second per gran f

at time of removal from reactor ii = number of atoms of target isotope per j

gram of dosimeter o = cffective crosg section at the semple location in em time in the reactor, sec q.

t

=

f g

~

1 = isotope decay constant, sec e

i 2

The total neutron fluence is then equal to ct in n/cm..A computer program is run to determine equivalent full power seconds from the power-time histograms, and to determine the appropriate saturation factor corrected for power fluctuations for each monitor.

...j The exact capsule location is necessary in that the effective cross section varies as a function of the neutron spectrum. ANISN, a. one i

dimensional, discrete ordinates transport code, is used to calculate the j

neutron spectrum at the capsule. From this data the effective cross sections for neutrons above 1 MeV are generated. Finally the total fluence,

't E >l MeV, for cach monitor is calculated.

i, N

3 i

~,-

4

'I i

14 i

Charpv Impact Properties i

The Charpy impact tests were conducted using a 240 f t-lb

)

Satec-Baldwin Model SI-1C impact machine in accordance with ASIM E23-72 The 240 f t-lb range was used for all tests. The velocity of the hammer.

at impact was 17.0 ft/sec. The calibration of the machine was verified i

as specified in AS7M E23-72 using Charpy impact specimens purchased from t

the U.S. Army Materials Research Agency. The results are listed in Table 3 f

TABLE 3.

CALIERATION DATA FOR THE BCL HOT LABORATORY f

C' HARPY IMPACT MACHINE

~

i

[

Average Standar

=

BCL Energy,

Energy, Variation Group ft-lb ft-lb Actual Allowed Low Energy 13.3 13.3 0 f t-lb il.0 ft-lb Medium Energy 49.0 50.7

- 3. 47..

5.0%

High Energy 74.7 77.3

-3.4%

• 5.0%

P (a) Established by U.S. Army Materinis and Mechanics Research Center.

l

i The impact machine is shown in Figure 6 The Velocometer and Dynamic Response Module associated with the instrumented Charpy testing are

?

mounted on top of the impact machine. The oscilloscope. located to the right of the machine is used to record load-time traces during impact tests.

ASIM procedures for specimen temperature control were utilized. The low temperaturc bath consisted of agitated methyl alcohol cooled with additions of liquid 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 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 at least - the ASTM i

recommended time.

i i

l

~. _ - -

. - ~

I 15 i

i l

i

. rM.

11 -

.s

~_.t_y.

i q-M

)

P.

O.

l N

O 9,, ;> e ~.

-~

l gA;q

... e e

\\

• to 1 j

e l

l

\\

l 4

1 l

N i

i 1

I q

l l

l C1914 l

i i

FIGURE 6.

INS *IRUMENTED CHARPY MACHINE i

Velocometer and Dynamic Response Module are shown mounted on top of the Charpy impact j

machine.

i l

5 I

i-i

}

l i

i i

8

-._..,,n.

+, -

~

f 16-

s 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 above 70 F was oil.

The specimens were manually transferred from the temperature bath to the anvil of the impact machine by neans of tongs that had also been i

brought to temperature in the bath. The specimens were removed from the bath and impacted in less than 5 sec. The energy required to brenk 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 l

of the fracture surface, and comparing the appearance of the specimen to an-ASIM fracture appearance chaIrt.( }

^

t Hardness Properties l

Hardness tests were done using a Wilson Rockwell hardness testing

.l i

nachine.

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 s

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 surf ace 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.

l ball penetrator on the specimen surface. The major load was then applied, and the resultant dial hardness readings recorded.

Af ter hardness readings were completed on the Charpy impact i

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 1

)

i I

.~

-f l

17 i

Tensile Properties l

The tensile tests were conducted on a screw-driven Instron I

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 h

strain. gage extensometer. The strain gage unit senses the differential movement of two extensometer extension arms attached to the specimen gage length 1 in, apart.- The extension arms are required for thermal protection l

of the strain gage unit during the elevated temperature tests. Figure 7 j

shows the extensometer extension arms and strain gage assembly used for-l tensile testing. The strain gage unit is shown at the bottom of the figure next to the region of the extensometer anms where the unit is attached during. testing. The extensometer was calibrated before testing using an j

Instron high-magnification drum-type extensometer calibrator.

l The irradiated tensile specimens were tested at room temperature and 550 F.

Elevated temperature tensile tests were conducted using~a j

three-zone split furnace. The specimens w'ere held at temperature before l

testing to stabilize the temperature.

Te=perature was monitored using a

{

Chromel-Alumel thermocouple in direct contact with the gage section of x

i the specimen. Temperature was controlled within i5 F.

E The load-extension data were recorded on the testing machine

.i strip chart. The yield strength, ultimate tensile strength, uniform I

elongation, and total elongation were determined from these charts. The i

t reduction in area was determined from specimen measurements made using a vernier caliper.

i f

i i

j I

l l

3 18 i

1 l

i 4

1 5

4 i

4 i

5 l

~i. ~

i mw..

=,.

f)

~ >r r

i

+

l t

P4973 I

FIGURE 7.

EKTENSOH'r IER EXTD4SION ARMS AhT STRAD4 GAGE ASSD(BLY USED FOR TENSILE TESTING b

i

+

'f 19 e

RESULTS AND DISCUSSION Neutron Dosimetry i

.5 Dosimeter wires from the two capsule basket assemblies were recovered and analyzed as described in the experimental-procedures. ll

]

total of 12 iron and copper. wires were gamma counted:

two of each from the wall region capsule basket pssembly, 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.

i An average total integrated f ast fluence greater than 1 MeV from 16

+

the iron dosimeters from the wall region capsule basket of 1.73 x 10 2

n/cm was obtained. Good agreement was obtained from the-copper dosimeters 16 2

at 1.86 x 10 n/cm. Generally, the iron value is considered more reliable i

due to its better known nuclear properties such as cross section-neutron

{

energy relationship and threshold energy. The top core area showed a large variation within the individual Charpy capsules. The measured iron 7*

18 2

19 2

4 fluence greater than 1 MeV ranged from 4.83 x 10 n/cm to-1.27 x 10 n/cm,

18

?

1 with an average value of 9.75 x 10 n/cm.

s The activation of the dosimeters in the water-filled annulus between the thermal shield and pressure vessel wall of the reactor' depends.

j 1

on the power history of the reactor and on the local neutron energy spectrum.

j In general, the activation of the dosimeter while it is in the reactor is

.y i

I I

=

T

)

[ c(E)^ (E, t)).e '(t-T)]

(1)

A=n

[ dE le dt o

o where 3

A = activity, disintegrations /cm. sec j

3 s

n = dosimeter nuclei concentration, atoms /cm

j i

E = neutron energy, NeV c(E) = reaction cross section, cm t-time, sec f

T = length of time the' dosimeter is in the reactor, sec

~1 1 = dosimeter decay constant, sec 1

~

l I

20 TABLE 4 QUAD CITIES UNIT NO. 2 FAST NEUTRON l

DOSIMETRY RESULTS

i

.i i'

Capsule

Fluence, Fluehee, Basket Charpy Mn Activity (I)

E>l;}eV, Co Activity ( ),

E >l tieV, j

O 2

Assembly Capsule dps/mg n/c=

dps/cg n/cm

,j 16 No. 13 G10 28.6 1.69x10 1.97 1.99 10 16 10 No. 13 G11 29.'9 1.77x10 1.71 1.73x10 16 16 i

Avg Value 1.73x10 Avg Value 1.86x10 t.;

9 No. 12 G10 13,060 1.27x10 '

420 1.58x10 9

19 No. 12 Gil 12,820 1.25x10 411 1.54x10 1

9 No. 12 G12 9,206 0.897x10 316 1.19x10 19 19 t

No. 12 G13 4,903 0.483x10 185 0.693x10 19 19 i

Avg value 0.975x10 Avg Value 1.25x10 (1) At reactor shutdown date of 12/22/74.

i

.I i

e i

t

-l 21' t

t i

2 t(E,t) : time and energy dependent neutron flux, neutrons /cm.'sec=MeV.

The neutron flux $(E,t) is separable in time and energy. Thus C(E,t) = N(E)}{t)

N(E)F(t)l,

(2)

=

where 1

r N(E) = neutron energy spectrum, MeV 2

i i = neutron flux at full reactor power, neutrons /cm sec F(t) = fractional power level at time t.

t Assuming F(t) = F'3 is-constant during a time interval, Tj, Equations (1) and l

.1 (2) are combined to give

{

=

A = nl [ [ dEc(E)N(E)] C, (3)'

I

~I uhere J

-XT

- A (T-t )

C=

Z F. (1 - e 3)e 3

~

= activation correction factor, 3

j=1 e

th t = the elapsed time at the end of the j time interval, sec j

J = number of time intervals, r

The neutron flux and reaction cross section are defined in terms of the " fast

'f flux" or neutron flux above 1.0 MeV as a

fc(E)N(E)dE

~

c(E)N(E)dE = E

=#

e (4) f f

p, I

o p

I U(E)dE I'.0 MeV r

l where f=3 f

N(E)dE = flux above 1.0 MeV S

1.0 MeV c = average reaction cross section above 1.0 MeV.

p P

9

.=

.u 22 i

i In summary, the dosimeter activation at the time of removal from the reactor is A=ner fR where C, O, and o are defined in Equations (3) and (4). Equation (5) f g

-A0 must also be multiplied by e to account for decay after removal of the dosimeter from the reactor, where B is the additional decay time between the

'l dosimeter removal and counting. Values used in the calculations are

-l summarized in Tables SA and 5B.

The values of the cross sections, c, to be used for calculations R

for the surveillance capsules were obtained from the report, " Comparative Analysis of the Pressure Vessel Surveillance Requirements-for Commonwealth Edison Power Reactors".(

ANISN calculated neutron spectra at two locations are shown in Figures 6 and 9.

From the time-history data the total number of equivalent full power days (at 2511 Mw(t) f ull-power icvel)-

was 596.5 days up to the shutdown date of December 22, 1974.

4 2

l i

5 l

l

)

i i

~

23 2

VALUES USED IN QUAD CITIES UNIT NO.

TABLE SA.

DOSIMETRY CALCULATIONS Product Saturation Threshold Targe; Half-Energy F actor Isotope %

Life MeV Abundance Target Reaction 0.185 5.26y 5.0 69.17 1007. Cu 0.589 Cu(n,0)60 63 Co 314d 1.5 5.82 100% Fe 54,

)S4Mn 7

FOR ACTIVATION CROSS SECTIONS IN BARNS TAELE 5B.

QUAD CITIES UNIT NO. 2 63 54 Cu re

>l MeV

>l McV Location 0.00113 Capsule 0.143 Near core top No.12 Capsule Basket guide, O' f

0.00420 Assembly (C 2) 0.236 l

Near Wall, 35*

1

' : No; 13 Capsule Easket

<Aosembly (G1)

.'*W

\\'.

4

r'!

f 23 p '

+

i i

TABLE 5A. VALUES USED IN QUAD CITIES UNIT No. 2 DOSIMETRY CALCULATIONS

't Targe; Threshold Product i

Isotope 7.

Energy Half-Saturation.

l Reaction Target Abundance MeV Life Factor e

t 63Cu(n,n)60 Co 1007. Cu 69.17 5.0 5.26y 0.185 54Fe(n,p)5'Mn 100% Fe

.5.82 1.5 314d 0.589 l

s

.b TAELE 5B.

ACTIVATION CROSS SECTIONS IN BARNS FOR QUAD CITIES UNIT NO. 2 i

I 54 63 Fe Cu

+

Capsule Location

>l MeV

. >l MeV i

No. 12 Capsule Basket Near core top 0.143 0.00113 7

Assembly (Cl) guide, O' j

t No. 13 Capsule Easket Near Wall, 35' O.236 0.00420 i

Assembly (G1) mm.--

y t

i I

5

N QURO-CITIES 142 2511.

BWR NERB WRLL (35,2151 i i11i1;:l i iillii:l 1 iIillii iitillil1itilli.l1lilli!)iiliiiiij i i littii i iliiii) i iiii 10 i i ilili D

10'*

}O tL tu I

T a

I Lt.1 C

c-Z 1 0', '

o T

C T

g D

2

[

to

-1 I

i 10 i i i tii'i i i iriir:

i iiiiiri i i ritirii i iiiiiii i iiritri i iiiiii!

1.1 iiiii i i siirit i i iirriti. i i ititi:

10

10'"

10

10'"

10*

10

10" 10" 10' 10" 10' 10'

~

~

~

NEUTRON ENERGY (MEVI-FIGURE G.

CALCULATED NEUIRON FLUX SPECTRMI AT. 35' NEAR-WALL CAPSULE BASKET ASSDiBLY i

~ LOCATION (AFTER BRASHElt AND THIMONS) 4

.t

a-0 25' r

C

~1 E: 1I i t 1 I

I ilII I i i!

I Iii C i ! i 1.

=.

~

~

I I

C e

,'=_

A

~

sc b

~

O.

m i

k

[

E v-4 i

s F

E u

i

'k es D

M i

g 3

E ir-J Z.

C M

i 3

~

b 7

a

_tc.

+

s --

- E.

o O

C E

y C

=

2 C3 g

~

N N

D a

s o

Cd A

=E-

=.

H D'E E

U O

I o-'

O m-t r) n c:

O >w--

i o

N 0 v

D g

g a g-p l-

.y

. sJ a

s

-Z-f*

N W H

O 1.L.I.

ev CC

._ ~

Od E

z-

-o

. L4.

u W

y

'cc 8m

_u cc o

mm F-mz s g s--

-E-g g

o I--

W 5 5

- r; E H z g-a T.4 Z

NH g.

.._ yO

=a g

-ou.

s-

-n.g O

=

=

C b

a x=

D

'O

' C3 <

$ [6

-T-iU e-*

-5 E

s pb

• 3 OH C

.Yh o-a

=

C

• .81W M

O O

^O m

III I I I I

I lII I I I l I

!!l I I I I I'

C M

f9

~

~

n C

3 4

4 b.

O O

O O

m.

N m.

-e XnlJ 3 A11U 19U NOUinJN 8

i

~.

i 26 I

Charov Ienact Prooerties 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 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 estimated fracture appearance [or each specimen. The lateral expansion is a measure of the deformation 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 l

o fracture appearance is a visual estimate of the amount of shear or ductile type of fracture appearing on the specimen fracture surf ace.

t

!ae impact data are graphically shown in Figures 10 through 14 These figures show the change in impact properties as a function of tempera-ture, including both the impact energy and the lateral expansion. Of particular interest is the temperature corresponding to the impact energies of 30 and 50 ft-lbs.

The energy level of the upper shelf is also of interest. Curves are drawn through the points corresponding to unirradiated data and the higher fluence Capsule G-1 data, but not through the points -

corresponding to the lower fluence Capsule G-2 data.

Figures 15 through 22 show the fracture surfaces of the Charpy specimens. Figure 16, as an example, shows how the fracture surf ace changes as the test temperature is increased for base metal specimens. The -30 F specimen (T2M) shows an almost flat fracture surface, with only 5% shear fracture appearance. This specimen absorbed only 8.0 fr-lb of energy during

{

the impact test, a typically low value for the low temperature, brittle region cf the Charpy curve. As can be seen in the figure, the amount of lateral expansion is moderate, and was measured as being 8.0 mils. As the test temperature is increased, specimens show an increasing amount of shear fracture appearance. The +295 F specimen (T43) fracture surf ace is typical of the type seen at the higher temperature end of the Charpy transition curve.

)

i

t

.(

27 TABLE 6.

CIIARPY V-NOTCH DIPACT RESl*LTS FOR f

QUAD CITIES UNIT NO. 2 BASE METAL e

SPECDENS FROM CAPSULE G2

?

)

Test Impact Lateral l

Temperature,

Energy, Expansion, Appearance,

[

Specimen F

ft-lb mils Percent. Shear.

-l T4K

-30 18.0 16.5 10 T2A

-20 21.5 22.5 10 A

i T4Y 20 49.5 40.5 20

- i T4U 25 76.5 62.0 50 T3L 78 103.0 70.5 75

~i T3B 150 135.5 92 0 100 T4J 220 131.0 89.0 100 T4C 295 137.5 89.5 100

[

TABLE 7.

CHARPY V-UOTCH H: PACT RESULTS FOR l

QUAD CITIES UNIT NO. 2 BASE METAL SPECHENS FROM CAPSULE G1 P

i Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, Specimen F

ft-lb mils Fercent Shear-

]

T2M

-30 8.0 8.0 5

i T3K

-20 17.0 17.5 5

T3C 20 25.0 26.5 10 T47 25 32.0 29.0 15 T4A 78 55.5 49.5 30 T4M 78 71.5 54.0 40 i

T25 225 120.0 88.0 100 T43 295 123.5 94.0 100 q

4

~

l

. i 28 f

TABLE 8.

CHARPY V-NOTCH IMPACT RESULTS FOR QUAD CITIES UNIT NO. 2 ESW UELD METAL

- l SPECIMENS FROM CAPSULE G2 Test Impact Lateral Fracture

' i Temperature,

Energy, Expansion, Appearance, Specimen F

ft-lb mils Percent' Shear T6C

-30 14.0 16.5 5

i TCL

-10 15.0 16.0 5

1

- t TB2 20 49.0 44.5 20 1

f TAM 25 41.0 38.5 50 T67 78 95.0 69.0 75 f

T64 78 93.0 70.0 75 T7D 220 108.5 89.O' 100-TAJ 295 103.5 79.0 100 i

TABLE 9.

CHARPY V-NOTCH IMPACT RESULTS FOR f

QUAD CITIES UNIT NO. 2 ESW WELD METAL

{

SPECIMENS FROM CAPSULE G1 l

Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance,

{

Specimen F

ft-lb mils Percent Shear T7C 20 6.5 11.0 0

T61 25 20.0 17.5 8

T62 78 34.5 35.0 20 T6.5 80 48.0 44.0 20 T7A 150 46.5 45.0 45 4

]

TBJ 220 77.0 74.0 80 T6A 295 90.0 79.0 100 T6T 340 88.5 81.0 100 E

i l

i s

m.

I l,

29 i

TABLE.10.

CHARPY V-XOTCH IMPACT RESULTS FOR QUAD CITIES UNIT NO. 2 ESW HAZ METAL l

SPECIMENS FROM CAPSULE G2 l

l l

Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, Specimen F

ft-lb mils Percent Shear l

DL1

-80 11.5 11.0 2

-l TMK

-30 36.5 37.0 20

i na

-20 75.5 57.0 30 nI2

-10 54.0 45.0 20

-- l ntB 20 74.0 56.0 25 n!3 78 114.0 71.5 85 l

TMP 220 120.0 83.0 100 l

f TM5 295 94.0 82.0 100 i

3 TABLE 11.

CHARPY V-NOTCH DIPACT RESULTS FOR j

QUAD CITIES UNIT NO. 2 ESW HAZ METAL SPECIMENS FROM CAPSULE G1

=i l

Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, Specimen

.F ft-lb mils Percent Shear nE.

-30 14.5 18.0

'10 TMT

-20 18.0 25.0 5'

)

Tlfi

-10 20.5 19.5

-5 l

TMC 20 66.0 54.0 35

~

TM4 35 42.0 38.5 20 Tt!6 78 82.0 64.5 70 i

TMD 78 112.0 77.0 80

-l TM7 225 96.0 83.5 90 i

TLT 295 133,5 88.5 100 R

f Ia

-t 30 l

('

TABLE 12 CIMRPY V-NOTCH IMPACT RESULTS FOR QUAD CITIES UNIT NO. 2 SAW WELD FETAL SPECIMENS FROM CAPSULE G1 l

i i

Test Impact Lateral Fracture Temperature,

Energy, Expansion, Appearance, j

Specimen F

ft-lb mils Percent Shear j

U4M

-30 3.0 4.0 0

i

~

U4L 20 3.0 2.5 0

U4P 78 12.0 25.0 10 f

U4C 150 24.5 27.5 65 U3U 150 24.5 31.0 45 U4A 220 29.0 35.5 65 l

U4R 295 43.0 50.5 100 I

U3 D 295 51.0 56.0 100 I

t i

TABLE 13.

CHARPY V-NOTCH IMPACT RESULTS FOR

)

QUAD CITIES UNIT NO. 2 SAW IMZ METAL SPEC 11 ENS FROM CAPSULE G1

-j i

n.

-Test Impact Lateral Fracture

~.

Temperature,

Energy, Expansion, Appearance, f

Specimen F

ft-lb mils Percent Shear U6E

-30 11.0 12.0 15 I

i UCA

-10 12.0 15.5 15 l

UCD 20 50.0 46.0 30 l

UAM 78 39.5 40.0 40 l

P U6B 80 31.5 32.5 30 j

UA1 225 60.0 61.0-60 I

?

U6; 295 62.5 65.0 100 U7P 2 95 67.5 69,5 100

^

i i

,. - -. ~.

32 10 0 i

i i

i 0

/

- 80,

/

=

0/

/

~

8

/

-60 '@

~

/

E f[

o O

I 40 $

/0

/

3'

/

/

20

/ 00

/

b

/

120 7

/

/

0 7

D 10 0

/

B

/

/

A

/

80 g

h

/

I E 60

/

5

/

P a

n u

h40

/ O

.=

/

/

-- Unitrodioted

/

20 -/

O Capsule G2

/ 00

/

-V Copsule GI g

i

-i i

i o

-10 0 0

10 0 200 300 400 Temperature, F TICU1'E 11.

ClGRPY IIIPACT PROPERTIES VERSUS TCIPEPXna'RE FOR QUAD CITIES U :IT 1:0. 2 ESW k' ELD NETAL

31

!OO 1

1

.i i

i O f,, _

i

/

- 80 i

/

.e i

U 5

/

Of

- 60 8-1

/

c g

j W

- 40 3

- r m

14 0

/

-8 C

G

- OgO 20

/

,/g

/

120

/

O 10 0 f

/

I n 80 Ol L

/

~

/

-9 g 60

/

c w

a y 40;-

f Unirradicted

/

O Ccpsule G2

/

t J._r-Copsule GI 20

- /'

/

/

I I

I O

-10 0 O

10 0 200 300 400 Temperatur5, F FIGURE 10.

CIBRPY DiPACT PROPERTIES VERSUS TE1PERATURE FOR QUAD CITIES WIT 50. 2 InSE METAL

33-10 0 l

1 I

4 i

A f'

O 80

/

c

/ A

.52

/

60 E O

g.

/9 5

6

- 40 s o

O

/

/

/

/

/

/

t 14 0 a

/

- 20 j

f

/

i

/

i j

t

-0 12 0' 7

0 l

l

/

i 10 0'-

/

/

A O

/

/

A 8 0.'

/

i E

D l

E O /a i

w

/

8 60' f

i a.

_E b

l 40r-

/

O 1

o 4

/

Unirradiated

/

20L- /

O Copsule G2

~

I

,0 o

Capsule GI I

O

-100 0

100 200 300 400 i

i Temperature, F FIGt'nE 12.

CliARPY DtPACT PROPERTIES VERSUS TDIPERA'UJRE FOR QUAD CITIES UNIT ED. 2 ESV 1MZ 11ETAL

1 34 1

1 1

1 1

10 0 80

._e

/

60-k

/

R

/

w

/

40 g b

5

-l

/

3

/

a

/

20

~

/

/

O a

0 100

~~

80 7

?

/

=

/

iso

/

e

/

o 5

/

O

~

8 40

/

c.s

/

/

a

/

20

/

-- Unirrodioted

~

f

/

,/

6 Capsule Gl I

O d

i i

i i

0

-100 0

10 0 200 300 400 Temperature, F FIGURE 13.

CHARFY DIPACT PROPERTIES VERSL'S TDIPERATURE FOR QUAD CITIES UNIT NO. 2 SAW WELD tiETAL i

i 35 10 0 l

i i

i i

i

./

/

80

/

u,

=

/

E-1

/

/

o 6 0 Tn

/

8

/

R

~

O /

/

- 40 8

/

a B

i

/

/

1 20

_/

?

100 f'

- 0

/

~

/

/

r

/

80

/

.o

/

G l

6 g50

/

a>5 a/

T3

/

g40 -

I e

/-

O j

/

201-

/

Unirradiated

/

'/

g A

Capsule Gi 0-10 0 0

10 0 200 300 400-Temperature, F FIGURE 14, CIBRPY LIPACT PROPERTIES VI2 SUS TDiPERATURE FOR QUAD CITIES C;1T NO. 2 SAW HAZ METAL

. - ~.

i t

i j

36 d

T4K T2A T4U T4Y Wi

,r y Mr iifW W

W "Y

T3L

' T3B T4J T4C l

1 i

i' FIGURE 15.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 2 IRRADIATED i

BASE METAL FROM CAPSULE G2 i

l I

i T2M T3K T3C T47 i

b Mi pl E i

l 3hi i

c

+

m.

T4M T4A T25 T43 I

l' FIGURE 16.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR QUAD CITIES UNIT NO. 2 IRRADIATED l

BASE METAL FROM CAPSULE G1 i

l I

\\

\\

l l

l I

l l

2.---

~

i

__l j

4 i

37 1

1 l'

T6C ICL TB2 TAM i

e sumum m

Y En Ed M Fi

}

w

-tr*

l T67 T64 T7D TAJ i

FIGURE 17. CIRRFY IMPACT SPECIMEN FRACIURE SURFACES j

FOR QUAD CITIES UNIT NO. 2 IRRADIATED i

l ESW WELD METAL FROM CAPSULE G2 l

i 4

l l

I T7C T61 T62 T65 i

i 1

q w.y

% s,.

\\

l T7A TBJ T6A T67 l

l

.i FIGURE 18 CIMRFY IMPACT SPECIMEN FRACTURE SURFACES i

FOR QUAD CITIES UNIT NO. 2 IRRADIATED j

l ESW WELD METAL FROM CAPSULE G1 i

l l

l l

I i

i i

~,,

aan A

A

-'M n

a we aa.-m4 s

a,..

.g a

-u.

1 38 T!U TMK TMM TM2 c 'q W

i l

EW"W L.,f I

l w

j L_

%4 M

M W

M FIGURE 19.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES l

FOR QUAD CITIES UNIT NO. 2 IRRADIATED j

ESW HAZ METAL FROM CAPSULE G2 i

l i

i I

i l

IME TMT TMY TMC TM i

h

?

l h]. S M M W k

21

(

Y

~.

'IM6

'IMD

'IM 7 TLT I

3 FIGURE 20.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES l

FOR QUAD CITIES UNIT NO. 2 IRRADIATED l

ESW HAZ METAL FROM CAPSULE G1 1

l i

4 i

k 1

39 d

l l

)

l U4M U4L U4P U3U i

I i

eft

~

I

~

t e s 1

U4C MA MK WD l

I FIGURE 21.

CHARPY IMPACT SPECIMEN FRACTURE SUPJACES FOR QUAD CITIES UNIT No. 2 IRRADIATED SAW WELD METAL FROM CAPSULE G1 l

U6E UCA UCD UAM 3_3

...e R-l.

s u

l

+'e I

,c s..

l l

U6B UAI U6K U7P l

t FIGURE 22.

CHARPY IMPACT SPECIMEN FRACTURE SURFACES l

FOR QUAD CITIES UNIT NO. 2 IRRADIATED SAW HAZ METAL FROM CAPSULE G1 1

k l

I

40 P

The fracture surface shows large shear lips with a 1007. shear fracture appearance. The specimen absorbed the relatively large amount of 123.5 ft-lb t

during impact. The substantial amount of plastic deformation occurring during this test is reflected in the large value of 94.0 mils lateral expansion.

Table 14 summarizes the 30 and 50 f t-lb transition temperature, the 35 mils lateral expansion temperature, and the upper shelf energy.

The I

unirradiated values for the base, ISW ueld, and the ESW IMZ materials are very close to the corresponding three materials which were irradiated in Capsule G2. (Capsule G2 was located near the inner surface of the pressure vessel wall, and therefore rece*1ved a relatively low fluence.) This is i

consistent with predictions made when the surveillance program was originally j

set up, and is due to the irradiation icvel for Capsule G2 specimens being too low to cause any appreciable impact property changes.(8)

In contrast to t.he Capsule G2 results, the impact properties of the.

higher fluence Capsule C1 specimens have been significantly shif ted due to the relatively high level of irradiation of this capsule.

The 50 f t-lb 1

transition temperature ranges from +30 to +325 for Capsule G1 materials. The highest value of +325 F is associated with the SAW weld material. Table 15 is a comparison of the unirradiated and Capsule C150 f t-lb transition tempera-l ture behavior. The lowest shift is the base metal change from an unirradiated value of +15 F to an irradiated value of +60 F, a transition temperature increase of 45 F.

The ESU IMZ, SAW 1%Z, and ESW weld materials have 50 f t-lb l

transition temperature shif ts of 50 F, 85 F, and 105 F, respectively.

The r

highest increase is the change f rom an unirradiated value of +40 F to an irradiated value of +325 F for the SAW weld metal, a change of 285 F.

In the figures showing Charpy properties as a function of tempera-ture, both the energy absorbed and the lateral expansion are plotted. The temperature shift at the 50 ft-lb level for each of the five materials irradiated in the higher fluence Capsule G1 is greater than the 35 mil lateral expansion temperature shift.

The upper shelf energy of a Charpy impact curve is defined as the upper Icvel of energy that curves exhibit at higher temperatures where increases in test temperature cause no further increase in impact energy. A

cneral eff ect of irradiation is to lower the upper shelf energy. The upper f

shelf cnergy Icvel for higher fluence Capsule G1 specimens ranges from rela-

~

tively low values of 51 and 67 f t-lb for SAW weld and SAW IMZ metals to and ESU IMZ higher values of 89, 123, and 133 F for the ESW weld, base, l

materials, respectively.

Cobah

- W w Gc t 1[7( unia.a.,

'D W % b % atuq TABLE 14 CilARPY IMPACT PROPERTIES FOR QUAD CITIES UNIT NO. 2 35 Mil Lateral 30 f t-lb 50 f t-lb Fhu Expansion Transition Transition Upper E >l MeV'

. Temperatures Temperature, Ternpe ra tu re,

Shelf, Material n/cm Capsule F

F F

f t-lb

. Base 0

Unitradiated

+10

-15

+15 135 16 Base 1.69 x 10 G2

+10

-10

+20 13$

gg Base 1.27 x 10 G1

+35

+25

+60 123 ESW Weld 0

Unitradiated

-5

-30'

+20 125 16 ESW Weld 1.69 x 10 G2

+10

'O

+30 107 ESW Weld 1.25 x 10 G1

+75

+65

+125 89 ESW llAZ 0

Unirradiated

-25

-45

-20 153 16 ESW IIAZ 1.77 x 10 G2

-35

-45

-15 120 79 ESW HAZ 1.25 x 10 G1 0

+5

+30 133 SAW Weld 0

Unirradiated

+20

+15

+40 90 yg SAW Weld 9.0 x 10 G1

+180

+195

+325 51 SAW HAZ 0

Untrradiated

+30

+10

+45 103 18 SAW HAZ 4.B x 10 G1

+55

+40

+130 67

42 Y

TABLE 15.

30 FT-LB AND 50 FT-LB TRANSITION TDiPERATURE SHIFTS DUE TO IRRADIATION FOR QUAD CITIES UNIT NO. 2 NEAR-CORE CAPSULE G1 30 ' f t-Ib 50 ft-lb~

Fluence, Transition Transition E>l$yeV, Temperature Temperature Material n/cm Shif t, F Shif t, F Base 1.27 x 10 40 45 ESU Weld 1.25 x 10 95-105 1

ESW HAZ 1.25 x 10 50 50 18 SAW Weld 9.0 x 10 210 285 SAW 11A7 4.8 x 10 30 85

~

f

-l

~

i 43 r

I As discussed earlier, the four Charpy capsules from capsule j

basket assembly No.12 (Capsule G1). did not receive a uniform neutron 18 exposure.

The exposure based on the iron dosimeters ranged from 4.83 x 10 18 to 12.7 x 10 nyt (>l MeV). For discussion purposes, an average value of the four iron dosimeters of 9.8 x 10 nyt can be used. However, particular 1

exposure values can be assigned to each of the five materials. Those l

specimens of a particular material located in two capsules were usually in adjacent capsules. Using a conservative approach of assigning the lowest neutron exposure received by any specimens of a particular material, the 18 five materials received exposures as follows: base,12.7 x 10 nvt; 18 18 18 ESW weld,12.5 x 10 nyt; ESW HAZ, 12.5 x 10 nvt; SAW weld, 9.0 x 10 nyt; i

nyt(*. Transition temperature values used in l

and SAW HAZ, 4.8 x 10 following figures are plotted based on these exposures.

The transition temperature shif ts for the irradiated materials are shown plotted in Figures 23, 24, and 25 as a function of fluence.

s-Figure 23 is the 30 f t-Ib shif t curve from the ~ General Electric surveillance l

program report Figure 24 is the 30 f t-lb shif t, and Figure 25 is the 50 f t-lb shif t values obtained in other surveillance programs and the present (16-25) program.

The apparent large scatter in data among the various programs is not unusual. Note that the weld-metal values generally determine the upper bound of the trend band. The values used to form the trend band are those from programs where the irradiation temperature was genera 11y between 550 and 590 F.

It can be seen that the Figure 24 30 f t-lb transition tempera-l ture shif t values for the pressure vessel materials of the present program f all within the upper and lower bounds determined by most materials of other investigations, except for the SAW weld metal which is just above the band.

e

1 (a) One ESW HAZ specimen, TLT, was irradiated in a Charpy capsule with an' iron dosimeter receiving a fluence of only 4.8 x 10 nyt, but was 4

tested at a temperature having no ef fect on the 30 f t-lb or 50 f t-lb 18 transition temperature shift.

Therefore the value of 12.5 x 10 nyt is quoted for the ESW HAZ specicens, as all but one were in a capsule with an iron dosimeter receiving this fluence.

~

~

}

i i

l 44 i

CENERAL ELECTRIC SURVEILLANCE PROGRAM TEST RESULTS PLOTTED FOR COMPARISON WITH REFERENCE DATA DNPS-BASE t.1ETAL Q HUMSOLDT-DASE TAETAL h DNPS-WELD fAETAL

+ HUMBOLDT-WELD f.!ETAL h DNPS - HAZ 4 HUMBOLDT-HAZ O BIG ROCK - BASE lAETAL

~

$ BIG RDCK-WELD METAL O BIG ROCK - H AZ 650 g i i isisi i i i i s sii e

i i s iinig i i s ii44g i s a s ti.

i EXPERIMENT 600 f,tATERIAL CODE A

B C

D E

14,6,7 9

O O

O 550 12 V

V 13 8

8 8

15,B,9 E

D G

g o

500 33 y

k 10 A

]2

{g400 3

1.75x10 A

350 225'T g

5 PNPS BASE t.tETAL E

o E 300 V}

UPPER LIMIT FOR r

sso$r GE-swr e

E OPERATING EXPERtENCE

~

Ng

~

j E

200 Y

h 2

6 150 V

QO 3O hk A

o

+

loo CD 9[A A h

B 50 o

e,,,,t

,i9,d g

,,,,,,1

,,,,,,,l,,,,,,,,,

D 20 I0 17 18 10 10 gg21 10 10 10 INTEGRATED NEUTRON DOSAGE ( > 1 MeV)(ht), hvt FIGURE 23 THE EFFECT OF 1RRADIATION ON VARIOUS HEATS OF A302B/A533B (AFTER BRANDT AND HIGGINS)

I 45 t

l l

i i

i i sii; 1

1 i

i isij Base Y! aid HAZ Point Beach No.1 0

4 4

Coaasciicut Yenhee O

G 300 Big Rock Point V

V V

Hurnbolt Bay C>

San Onofre

<3 4

4 Dresden No.2 C

4

-G t

Dresden No.3

' EF G-E-

Quod CitiasNo.1 d

8 C

Occd Cities No.2 (1

9 G

Y Yankea Surveillance A

Ycnkee Special 0

q u-3 f 200 S

V 5

9

~

i

/

y O

]

9 g

E

/

N

/

{

-6 l

4 \\

&@6 9

10 0

=N o 44

/

o Q

b W

-a w

L.

q y

~,

a 4

Nha i

r_,

g)N 7 Trerd ' Band For 550-590 F

~

O i

t I

i-'I I

i i

iI 8 8' I'I

j w

20-13 10'3 10 13 Neutron Fluence, nyt FIGl!!!! 24 ColiPARISO:: or 30 FT-Ln '1TvC:SITION TCPI2tA11?,E VALUEg Fl:0)1 VAllIOUS SURVEILL'.?;CE P200 rah 5 FO'.; A307 l

CRADE 11 PitESStHIE VE53rL STEEL i

P

p t

46

]

1 f

l-j ij i

i 8

i 1 i a

i 1

.4 a

4 i

Bcse Wald HAZ l

i 1

Point Bacch No.1 O

4-4'

-I i

300-Connecticut Yankae O

o G

. -)

j g

l H. B. Robinson D

4 t

Dresden No.2 C

-3

-E 1

l i

Dresden flo.3 D

E-

i m

Si Qucd Cities No.1 d

!lil

-I e

e Quad Cities No.2 Q

B 9

l' o

5 g

es

-E5 200,-

4 I

o

$3

-23 5' F ca.

E y

I c:

i o

4C

.=

C d m

8

-a i

~g l

o N

- 100<-

0

-D i

e o

9g in O

y 9

G Er G

0E DQ l

o O

s i

u i

D l'

0 13 3

20 10 10

-10 l

Neutron Fluence,nyt.

i 1

FIGURE 25.

COMPARISON OF 50 FT-LB TRAKSITION Tf2IPE:1ATURE-SHIFT VALUES FROM VARIOUS SURVEILLAECE PROGA11S FOR SA302 GV.DE B PRESSURE

]

VESSEL luTERIALS I

o I

l l

1 b

47 j

l Hardness Properties Rockwell B hardness measurements were made on all materials for each of the two capsules. Hardness measurements were made on three specimens for each material. Table 16 lists the individual readings.and l

the average readings.

Table 17 is a comparison of the irradiated results'from this j

program with the unirradiated results,from the base line program.(10). Each 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 hardness of unirradiated and Capsule G2 specimens for a particular

{

material are essentially identical because of the low neutron fluence of Ccpsule C2 specimens. However, the average hardness of the higher fluence Capsule G1 specimens in comparison to that of the unirradiated specimens is f

appreciably increased for each of the five materials. This is typical behavior f

for pressure vessel steel after appreciable irradiation.

f P

r.i i

i

)

i

?

b 48 f

TABl.E 16.

IMRDNESS PROPERTIES OF QUAD CITIES I

UNIT NO 2 IPJtADIATED SPECDIENS Individual liardness Readings, Average Rockwell B Hardness Material Capsule Specimen No. 1 No. 2 No. 3 No. 4 No. 5.

Rockwell B.

l Ease G2 T4K 90.2 91.8 91.1 92.1 90.6 91.2

{

Base G2 T4U 91.8 90.5 91.1 90.7 90.0 90.8 Base G2 T2A 89.2 89.6 90.1 90.7 90.4 90.0 ESW Weld G2 TAM 88.0 87.7 87.7 88.1 88.3 88.0 ESW Weld G2 TCL 88.2 88.4 88.8 88.4 88.3 88.4 ESW Weld G2 T64 88.1 87.7 88.0 88.3 88.0 88.0 ESW ImZ G2 D15 88.1 88.4 88.4 88.3 87.9 88.2 f

ESW Inz G2 D12 87.0 87.9 87.7 87.3 87.5 87.5 ESW IMZ G2 DiJ 87.3 88.3 88.6 88.7 88.1 88.2

[

Base G1 T4A 93.3 93.6 93.8 92.8 93.9 93.5

+

Base G1 T3K 92.2 92.6 92.9 94.0 93.0 92.9 Base G1 T47 93.0 93.3 93.8. 93.5 92.0 93.1 SAW Weld G1 U3U 97.8 98.6 98.2 98.0 98.7 98.3 SAW Weld G1 U3D 97.6 97.1 97.3 97.0 97.4 97.3 SAW Ucid G1 U4K 97.8 97.4 97.5 97.2 97.0 97.4 SAW 1RZ G1 UCA 96.8 97.7 98.2 97.0 97.7 97.5 SAW IRZ G1 U7P 97.7 98.0 98.3 98.8 98.5 98.3 SAW IRZ G1 U6E 97.3 98.2 97.3 97.5 97.9 97.6 ESU Wcld G1 T61 93.7 93.6 94.2 94.0 94.0 93.9 ESW Weld G1 T6T 93.8 94.8 94.3 94.2 93.5 94.1 ESW Weld G1 T65 94.8 94.6 94.1 94.9 94.8 94.6 ESU inZ G1 DiY 92.3 92.8 92.8 93.2-

.92.9-92.8 ESW InZ G1 D14 91.3 92.7 93.1 93.3 92.9 92.7 ESW IIAZ G1 D16 93.0 93.3 93.8 93.4 94.0-93.5 i

t

i 49 TABLE 17.

CG1 PARIS 0N OF UNIRRADIATED AND IRPdDIATED AVERAGE 11ARDNESS RESULTS FOR QUAD CITIES 3

UNIT NO. 2 SPECIMD5 Average Hardness,(a)

Material

Capsule, Rockwell B-

}

Base Unirradiated 91.5 t

Base Capsule G2 90.7 Base Capsule G1 93.1 ESW Weld Unirradiated 89.1 ESW Weld Capsule C2 88.1 ESW Weld Capsule G1 94.2 ESW RAZ Unirradiated 89.5 ESW HAZ Capsule G2 88.0 ESW HAZ Capsule G1 93.0 t

SAW Weld Unirradiated 90.4 SAW Weld Capsule G1 97.7

.[

SAW HAZ Unirradiated 89.3 SAW 11AZ Capsule G1 97.8 (a) Average of three specimens, five hardness readings per specimen.

j l

f i

~!

i 1

l 1

' l

)

b i

..d

~

i c

50 i

Tensile Properties The tensile properties deternined'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 j

Posttest photographs of the tensile specimens are shown in Figures area.

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 ESW weld metal Specimen I D1 tested at 550 F.

j Tensile tests were run at room temperature (87 to 92 F) and 550 F.

The higher temperature tests exhibited a decrease in 0.2 percent offset yield

{

f strength and a decre'ase in ultimate tensile strength for each material, except for the SAW HAZ material which has a 550 F ultimate tensile strength y

slightly less than the room temperature value. In general, ductility values r

(as determined by total clongation and reduction in area) decreased at 550 F.

I as compared to 75 F for each materia 1.

The Capsule G1 tensile specimens were located in the vicinity of

-l 19 I

iron dosimeters which received fluences of 1.3 x 10 nyt, while the i

Capsule C2 tensile specimens were located in the vicinity of an iron i

16 dosimeter receiving a fluence of 1.7 x 10 nvt (E> 1 MeV).

i

.i I

i s

f i

i e

i s

TABLE 18.

TENSILE FROPERTIES OF QUAD CITIES UNIT NO. 2 IRRADIATED SPECIMDiS 0.2%

offset Ul timate Yicid,

Tensile Uniform Total Reduction

Temp, Strength,

Strength, Elongation, Elongation, in Area, Material Capsule

) Specimen F

psi psi percent percent percent Base G2 UDC 92 60,920 91,330 11.5' 24.9 70.8 Base G2 UD7 550 58,490 90,590 9.5 20.3 64.2 g

ESW Weld G2 UJK 87 59,180 85,410 10.4 22.4 62.0 ESW Wcld G2 UJ5 550 55,610 83,980 8.7 17.3 57.6 ESW Inz G2 UL2 92 58,740 83,990 10.0 23.2 70.3 ESW llAZ G2 ULA 550 55,610 81,740 8.0 18.2 60.4.

Base G1 UD3 91 71,270 98,980 10.3 21.5 66.7 Base G1 UD5 550 67,680 94,160 8.4 18.0 62.2 ESW Weld G1 UJJ 92 69,760 97,050 10.8 21.8 58.8 ESW Weld G1 UJT 550 63,320 91,800 8.4 17.2 52.7 ESW ltAZ G1 ULC 92 67,210 94,200 10.2 20.8 66.0 ESW.1RZ G1 ULB 550 62,630 S9,510 8.4 16.8 59.5 SAW Ucid G1 UP1 89 81,300 106,910 11.8 22.4 56.7 SAW Weld G1 UPB 550 74,085 99,240 10.7 19.3 54.7 SAW HAZ G1 UU1 90 73,680 98,480 7.3 15.6 59.3 SAW nAZ G1 UUC 550 71,280 99,390 8.3 16.2 58.2 (a) Capsule C2 and G1 tensile specimens were located in regions of iron dosincters receiving fluences in19 nir 2

,,,,,,,,,,3

,,.. in16, a i 2

.._,.....c

. ~..... - -

52 i

l l

Material: Base Capsule: G2 l

Specimen: UDC Test Temperature: 92F 4

l

-c-1 I

l l'

Material: Base Capsule: G2 l

Specimen: UD7 Test Temperature: 550 F

=

1 l

4 l

M..

Material: ESW Weld Capsule: G2 j

Specimen: UJK i

Test Temperature: 87 F l

l I

j Material: ESW Weld j

Capsule: G2 Specimen: UJ5 Test Temperature: 550 F i

FIGURE 26.

POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 2 l

TENSILE SPECIMENS i

1 i

l i

1

t i

53

~

Material: ESW HAZ Capsule: G2 l

Specimen: UL2 Test Temperature: 92 F i

-:f_

N 1

i i

I t

l Material: ESW HAZ l

Capsule: G2 l

Specimen: ULA i

Test Temperature: 550 F i

i J

I I

-^

Material: Base l

Capsule: G1 j

l Test Temperature: 91 F Specimen: UD3

)

1 i

i i

l l

I 3

Material: Base Capsule: G1 l

l Specimen: UD5 l

Test Temperature: 550 F I

l i

FIGURE 27.

POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 2 IRRADIATED TENSILE SPECIMENS I

i i

... ~._-.

. ~.

1 1

54 l

1 l

Material: ESW Weld Capsule: G1 l

Specimen: UJJ f

Test Temperature: 92 F 4

i i

Material: ESW Weld Capsule: G1 Specimen: UJT Test Temperature: 550 F i

l a

i l

i i

Material: ESW HAZ I

i l

Capsule: G1 l

Specimen: ULC Test Temperature: 92 F 5

i I

l

\\

Material: ESW HAZ j

Capsule: G1 Specimen: ULB f

Test Temperature: 550 F 1

l FIGURE 28.

POSTTEST PHOTOGRAPHS OF QUAD CITIES UNIT NO, 2 IRRADIATED TENSILE SPECIMENS l

l i

I l

1 55 l

l Material: CAW Weld Capsule: G1 Specimen: UP1 i

Test Temperature: 89 F j

1 1

)

1 j

1 Material: SAW Weld j

Capsule: G1 l

Specimen: UPB l

Test Temperature: 550 F i

i i

P i

i s

1 l

i Material: SAW HAZ i

Capsule: G1 Specimen: UU1 l

Test Temperature: 90 F l

l l

i l

Material: SAW HAZ l

Capsule G1 f

Specimen: UUC l

Test Temperature: 550 F l

i l

):

i I

FIGURE 29.

POSTIEST PHOTOGRAPHS OF QUAD CITIES UNIT NO. 2 IRRADIATED TENSILE SPECIMENS l

f

56 100,000 i

i i

- ?

t 75,000

-w a

E 50,000 en i

25,000 1

{

0 0

5 10 15 20 25 Percent Elongation j

I FIGURE 30.

TYPICAL STRESS-STRAIN CURVE Curve Shown is for ESW EAZ Specimen ULC Tested at 92 F, I

l l

i i

-e-----n

..-1

~+. m%

m

i f

57 i

CONCLUSIONS i

f The maximum neutron exposures received by Capsule Basket No.12 (Capsule G2) and Capsule Basket No. 13 (Capsule G1) were 1.8 x 10 n/cm

(>l Mev) and 1.3 x 10 ' n/cm

(>l MeV), respectively. The shif t 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-weld weld (SAW weld) metal, submerged-arc-weld heat-affected-zone (SAW HAZ) metal, electro-slag-weld f

weld (ESW weld) metal, and electro-slag-weld heat-affected-zone (ESW HAZ) metal. Capsule G2 values were essentially unchanged because of the relatively low fluence of these specimens. The 50 f t-lb transition temperature is in the range of 30 to 125 F for all Capsule G1 materials l

except the SAM weld metal. The SAW weld metal value is 325 F.

The upper i

shelf energy level of capsule G1 materials ranges from 51 to 133 f t-lb, j

with the value of 51 f t-lb being for the SAW weld metal, f

Hardness properties of Capsule C2 materials were essentially unchanged by irradiation, but Capsule G1 materials all show increases.

Tensile properties of Capsule G2 specimens were essentially r

unchanged by irradiation. However, tensile properties of Capsule G1 specimens showed significant changes. Both yield strength and ultimate tensile strength values generally are higher as a result of irradiation. The i

total clongation and reduction in area values are generally less than preirradiation values.

I t

I I

l F

s

58 PrrrPENCrs (1)

Reuther, T. C., and Zwilsky, K. M., "The Effects of Neutron Irradiation on the Toughness and Ductility of Steels", in Proceedines of Toward Troroved Ductility and Touchness Synoosius, published by Iron and 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 Weldsents", NRL Report 7176 (October 30, 1970).

(3)

Berggren, R. G., " Critical Factors in the Interpretation of Radiation Effects on the Mechanical Properties of Structural Metals", Welding Research Council Bulletin, 31, 1 (1963).

(4) Witt, F.

J., " Heavy-Section Steel Technology Program Semiannual Progress Report for Period Ending February 29, 1972", ORNL Report No. 4816 (October, 1972).

(5) Hawthorne, J.

R., " Radiation Effects Information Generated on the ASTM Reference Correlation-Monitor Steels", American Society for Testing and Materials Data Series Publication DS54 (1974).

(6) Steele, L.

E., and Serpan, C.

Z., " Neutron Embrittlement of Pressure Vessel Steels - A Brief Review", Analysis of Reactor Vessel Radiation Effects Surveillance Programs, American Society for Testing and Futerials 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).

(8) Higgins, J.

P.,

and Brandt, F. A., " Mechanical Property Surveillance of General Electric ERR Vessels", General Electric Report NED0-10115 (July, 1969),

(9) ASTM Designation E185-73, " Surveillance Tests on Structural interials 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.1 and Unit No. 2 Reactor Pressure Vessel Surveillance Programs:

Un-irradiated Mechanical Properties", Final Report to Connonwealth Edison Company (February 15, 1975).

(11)

ASIM Designation E263-70, " Measuring Fast Neutron Flux by Radioactivation of Iron", Book of ASTM Standards,.Part 45 (1974), pp 814-819.

59 1

\\

(12) ASIM Designation E523, " Measuring Fast Neutron Flux by Radioactivation of Copper", under preparation for. publishing in Book of ASTM Standards, Part 45.

(13) ASTM Designation E23-72, " Notched Bar impact Testing of Petallic Materials", Book of ASTM Standards, Part.10 (1974), pp 167-183.

(14) ASTM Designation A370-73, " Mechanical Testing of Steel Products",

Book of ASTM Standards, Part 10 (1974), pp 1-52.

i (15) Brasher, W. S., and Tiemons, D. H., " Comparative Analysis of the

+

Pressure Vessel Surveilla,nce Requirements for Connonwealth Edison Power Reactors", Final Report to Commonwealth Edison Company (November 1, 1974).

(16) 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).

(17) 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, and IV", NRL Report 6616 (Septecher 29, 1967).

1 (18) Brandt, F. A., "Humboldt Bay Power Plant Unit No. 3 Reactor Vessel Steel Surveillance Prograc!',. GECR-5492- (May,1967).

(19) " Analysis of First Surveillance Material Capsule from San Onofre Unit I", Southern California Edison Company (July,1971).

l 1

(20) 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 l'

Power Company (March 30, 1972).

(21) Perrin, J.

S., Sheckherd, J..W.,

Farmelo, D, R., and Lowry, L. M.,

" Point Beach Nucicar Plant Unit No.1 Pressure Vessel Surveillance Program:

Evaluation of Capsule V",

Final Report to Wisconsin Elcetric Power Company (June 15, 1973).

(22) Perrin, J. S., Farmelo, D. R., Denning, R. S., and Lowry, L. M.,

"Dresden Nucicar Plant Unit No. 3 Reactor Pressure Vessel Surveillance Program: Capsule Basket No.13, Capsule Basket No.14, and Neutron Dosimeter Monitor", Final Report to Commonwealth Edison Company i

(March 1, 1975).

(23) Perrin, J. S., Farmelo, D. R., Denning, R. S., and Lowry, L. M.,

" Quad Cities Nuclear Plant Unit No.1 Reactor Pressure Vessel Surveillance Program: Capsule Basket No. 2, Capsule Basket No. 3, and Neutron Dosimeter Monitor", Final Report to Commonwealth Edison Company (March 1, 1975).

j T

e

4 I

i

' ?

60 (24) Yanicako, S.

E., Lege, D. J., Anderson, S. L.,

and Hager, T. R.,

j

" Analysis of Capsule S 'from Carolina Power and Light Company H. B.- Robinson Unit No. 2 Reactor Vessel Radiation Surveillance Program", Final Report to Carolina Power and Light Company (December 1973).

i

.f (25) Rieger, G. F., and Henderson, G. H., "Dresden Nucicar Power Station Unit One and Unit Two Mechanical Properties of Irradiated Reactor' Vessel Material Surveillance Specimens", NEDC-1258.E (May 191A.

?

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,s APPENDIX A

'l r

l INSTRUMENTED CHARPY EKAMIKATION I

i t

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)

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)

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APPI2TDIX A i

INSTRLSIENTED CHARPY EX141IKATION f

INTRODUCTION The' radiation esbrittlement of an operating nuclear pressure.

vessel is determined by the accelerated irradiation of the original materials -

l as part of a surveillance program.

The lifetine of the pressure vessel vill l

depend on the radiation-induced shif t in the ductile-brittle transition temperature as measured by the 'Charpy V-notch impact test.

f The value of baseline unirradiated and irradiated Charpy impact

{

specimens, particularly in present surveillance progra=s, can be enhanced by the use of the instrumented Charpy test. The instrumented Charpy test l

provides a link between the, transition-temperature approach and the

~j fracture-mechanics approach to fracture toughness.- The results obtained by i

applying instrumented Charpy techniques to the unirradiated Charpy specimens for the surveillance program are presented in this section of the report.

~

EACKGR0"ND

'I i

There are two approaches to determining the effect of radiation on the fracture toughness of pressure-vessel steels: (1) the shif t in the f

ductile-brittle transition te=perature, and (2) the change in the fracture l

~

[

toughness (either the static fracture toughness K

the dynamic fracture y

I ** # I'#E ""I toughness (kid)*

fracture parameters such as friction stress, grain size, grain-size dependence

]

of the yield stress, and surface energy or plastic work of microcrack propagation. The effect of radiation en most of these netallurgien1 fracture parameters has been previously studied, but until recently, the results had not been directly linked with the radiation-induced change in fracture j

t toughness. This recent work established the relationships between the key j

(1)

• l metallurgical f racture parameters and the transition temperature and K 7

l i

• References at the end of this Appendix.

-l

=1 1

I l

1 i

A-2

-l l

The instrumented Charpy test is an excellent tool for determi-l nation of the ef fects of radiation on the key metallurgical fracture I

l parameters.

This test provides load-time information in addition to the l

energy absorbed. The loads involved during impact are obtained by instru-l 1

menting the Charpy striker with strain gages so that the striker or top

-j I

is essentially a load cell. The details of this technique have been l

l reported previously.(2,3) l The additional information obtained from the instrumented Charpy e

GY (P astic. yielding across the entire l

test is the general yield load, P cross section of the Charpy specimen), the maximum load, Pi,x, the brittle j

fracture load, P, and the time to brittle fracture (see Figure A-1).

The-F

.j area under the load-time curve corresponds to the total energy absorbed,

j uhich is the only data obtained in a normal uninstrumented Charpy test.

{'

The instrumented test, however, allous separation of the energy absorbed i

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 l

formation (postbrittle fracture energy), as shown in Figure A-1.

c In a normal Charpy impact study, the energy absorbed is determined as a function of temperature to obtain the Charpy impact curve and the

'l transition temperature. The instrumented Charpy test also gives the information shown in Figure A-1 as a function of temperature,' as shown by the example in Figure A-2.

Various investigators ( ~ } have developed t

theories that permit a detailed analysis of the load-temperatere diagram.

This diagram can be divided into four regions of fracture behavior, as shown l

In each region different fracture parameters are involved ( ).-

f in Figure A-2.

Extended discussions of these fracture parameters can be found in the references indicated above.

1 1

?

E

.l P

y 7

-.e

A-3 l

'i Mar.imum load, P

, General yield

' load, P b

gy Ilrittle fracture load, P F i

Pos t"maxieu:n-load"

)(}

m energy m

Post brittle-fracture x

energy I

tN f?RE"maxicm:n-1. cad" energy

>b 2X-3 -z Time to brittle fracture

' -l Tirae FIGURE A-1.

AI; IDEALIZED LOAD-TD:E HISTORY FOR A Cl!ARPY D1 PACT TEST r

s 9

+

A-4 r

i i

7 m

i

%g u

N P

g P

g F

u

,0, s.

,/

r mc p

[

i F

PGY

-o 3

.ca.

Region.1 Region 2 Region 3 Region 4 Te:t te=perature t

i FICURE A-2.

CRAPHICAL AID. LYSIS 07 CILA.RPY IUPACT DATA i

' I 1

, 1 I

\\

=

A-5 l

EXPERIMENTAL PROCEDURES

}

i

{

The general procedures for the instrumented Charpy test are the same as those for the conventional impact test, and are described'in I

the main text of this report. The additional data are obtained through a

]

fairly simple electronic configuration, as shown in the schematic diagram j

of Figure A-3.

j The striker of the impact machine is modified to make it a

{

dynamic load sensor. The modification consists of a four-arm resistance f

strain gage bridge positioned on the striker to detect the compression

]

5 loading of the striker during the impact loading of the specimen. The com-pressive clastic 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 ( ) 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-veld weld (SAW weld) metal, submerged-arc-weld heat-affected-zone (SAW llAZ) metal, electro-slag-weld weld (ESW weld) metal, and electro-slag-weld heat-af fected-zone (ESW 11AZ) metal. The results of the instrumented Charpy work uith the corresponding load-time records are given in Tables A-1 through A-8.

The tables list the sp'ecimen 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; houever, all tests fall into one of the six distinctive notch-bar bending classifications shown in Figure A-4.

4 4

A-6 i

/ a T

l s

Vl

/

i v

Bridge balance Oscilloscope and

-O amplifier Shunt Triggering resistance device l

Hamer 3-i e

i FIGURE A-3.

DIAGRA!! 0F INSTRUt!ENTATION ASSOCIATED WITH II;STRUMENTED CHARPY EXAMINATION

A-7 TABLE A-1.

INSTRUMEETED CPARPY HIPACT DATA FOR QUAD CITIES UNIT 1:0. 2 BASE METAL SPEODIEl;S FROM CAPSULE G2 5000 Specimen No. :

T4K 40N Test Temperature (F):

-30 "3000

2000!

Impact Energy (f t-lb):

18.0 General Yield Load, PGY (1b).

,3400 1000 Maximum Load, P (1b):

3800 0

1000 2000 3000 4000 5000 Time, psac 50M Specimen No.:

T2A 4000 Test Temperature (F):

-20 e

/

- 3000 Impact Energy (f t-lb):

21.5 E

3 2000 General Yield Load, Pgy (1b):

3150 1000 Maximum Load, P (1b):

3300 i

0 0

1000 2000 3000 4000 > 5000 Time, psee Specimen No.:

T4Y 5000

[

Test Temperature (F):

20 4000

1. 3000i-Impact Energy (f t-lb):

49.5 3100 32000 General Yield Load, PU (Ib):

1000

'4250 Maxit.itra Lond, Pmax (1b):

(

0 0 1000 5000 3000 4000 5000

~

Time, psec T4U M

Specimen No.:

25 4000

^

Test Tc.nperature (F):

3000(

Impact Energy (f t-lb):

76.5 j

7 3 2000 General Yield Lond, P W:

M gy 1000 4400 (Q

Maximum Load, P (1b):

0 1000 2000 3000 4000 0000 Time, psee

b A-8 TABLE A-1 (Continued) r Speciraen No.:

T3L

.5000 Test Temperature (F):

78 4000 3

1. M Impact Energy (f t-lb):

103.0 General Yield Load, PGY (1 )

1000 Mar.imun Load, P x (Ib):

4150 00 1000 2000 3000 4000 5000 Time,psac Specimen !!o.:

T3B 5000 Test Temperature (F):

150 4000 Impact Energy (ft-lb):

135.5

$3000 f General Yield Load, P N'

CY 1000 Maximum Load, P ax (1b):

4000 0

1000 2000 3000 4000 5000 Time, psec 5000 Specimen No.:

T4J 4000 Test Tcaperature (F):

220 g

- 3000 i

Impact Incrgy (f t-lb):

131.0 g

2000 s

2500 General Yield Load, PGY (1b):

y 1000 3750 Nanimum Load, P,x (Ib):

O 500 F3001 1500!. 2000* 2500 Time,pse:

T ',C 5000 Specimen No.:

295 4000 Test Temperature (F):

137.5 Q3000 f Impact Energy (f t-lb):

M General Yield Load, Pg7 (Ib):

\\

000 1:aximu:a Load, P (1b):

3QO

\\

ar 0

500, 1000 - 1500. 2000 ; 2500

~ Time, psec e

= = -

f 4

i t

A-9 TABLE A-2.

INSTRUMD'TED CMRPY DIFACT DATA FOR QUAD

[

CITIES UNIT UO. 2 EASE METAL SPECIMEMS FROM CAPSULE G1 Specimen No.:

T3R 5000 v

Test Temperature (F):

-20 4000 Impact Energy (f t-lb):

17.0

3000, S

General Yield Load, Pgy (1b):

3400 1000 14aximum Load, Pmax (Ib):

3800 o0 1000 2000 3000 4000 5000 Time, psee Specimen No.:

T3C 5000 Test Temperature (F):

20 4000

}.3000 Impact Energy (ft-lb):

23.0 General Yield Load, PCY (1b):

3200 3 2000 1000 Maximum Load, P (1b):

4050 O

1000 2000 3000 4000 5000 Time, pste Specimen Eo.:

T47' 5

,g 4000 Test Temperature (F):

/

,3000 Impact Energy (f t-lb):

32.0

-7 3 2000 3250 General Yield Load, Pg, (1b):

4300

!!n>:ieum Load, P*** (1b):

O 1000 2000 3000 4000- 5000 Time, psee i

b#

Specimen No.:

T4A 4000 g3000[

Test Terperature (F):

70 gh Impact Energy (f t-lb):

55.5 General Yield Load, PCY (

1000

\\

11aximum Load, P "* (1b):

4250 0'O 1000 2000 3000 4000 5000 Tama, psec

i j

A-10 TABLE A-2 (Continued) i 5000 Specirnen No.:

T4M E

Test Temperature (F):

73 g'000[

I Impact Energy (f t-lb):

71.5 f*

1 2000 General Yield Load, Pg (1b):

,2950

+

1000 Maxinum Load, Pmax (1b):

4200

(

0 0

1000 2000 3000 4000 5000 Time, psec Specimen No.:

T43 5000 -

4000 Test Temperature (F):

295 3000 Impact Energy (f t-lb):

123. 5 g

' 2000 General Yield Load, PGY (ib):

2500

\\

gogo

(

Mar.imt= Load, Pmax (Ib):

,3650 N

O 500 1000 1500. 2000, 2500 Time, psec i

f F

t

A-11 TABLE A-3.

INSTRUMENTED CHARPY DIPACT DATA FOR QUAD CITIES UIIIT NO. 2 ESW WELD METAL FRai CAPSULE G2 Specimen No.:

T6C 5000 4000 Test Temperature (F):

-30

[

3000 Impact Energy (f t-lb):

14.0 000 General Yield Load, PU (1b):

,3050 1000 Maximum Load, P (1b):

3500 0

1000 2000 3000 4000 bOOD Time psec Specimen No.:

ICL 5000 4000 Test Temperature (F):

-10

,3000l Impact Energy (ft-lb):

15.0 fo 2000 General Yic1d Load, PGY (1b):

3200 8

3000 Maximum Load, P (Ib):

3600 g

0 1000 2000 3000 4000 5000 Time, psee Specimen No.:

T32 5000 Test Temperature (F):

20 4000 8

Impac t Energy (f t-lb):

49.0 3000 y

[

3 2000 General Yield Load, PCY (Ib):

2900 1000 Maximum Load, P

(Ib)

3900 0

1000 2000 3000 4000 5000 Time,psec Specimen No.:

TAM.

5000 Test Temperature (F):

25 4000 g

3000 Impact Energy (f t-lb):

41"0 f

3 2000 General Yield Load, PU (1b):

3000 1000' Maximum Load, P (1b):

3950 C

0 1000 2000 3000 4000 5000 Time psec

A-12 TABLE A-3. (Continued) 5000 Specimen No.:

T6 '+

4000 [

Test Temperature (F):

78 e

Impact Energy (f t-lb):

93.0 General Yic1d Load, Pg7 (1b):

,2950 1000' Maximum Load, P * (1b):

3950 0

0 1000 2000 3000 4000 5000 Time.psec 5000 Specimen No.:

T7D

~

4000 Test Temperature (F):

220 8

(A(.

3000 Impact Energy (ft-lb):

103.5 7a 2000 2500

\\

8 General Yield Lond, PGY (ib):

1000 Maximum Load, P (1b):

3500

\\

0 500 1000, 1500 2000 2500-Time, psec TAJ.

5000 Specimen No.:

4000 Test Temperature (F):

295 I \\

Itapact Energy (f t-lb):

103.5

'250 General Yield Load, Pg (Ib):

1000 3000 g

Mc:ciewn Load, Pmax (1b):

0

\\-

0 500 1000 1500 2000 i 2500 Time psec

= =.

l 3

t 1

t

-l A-13 i

TAELE A-4.

IliS'IRUMENTED CHARPY DIPACT DATA FOR QUAD CITIES UKIT KO. 2 ESW WELD METAL FRai CAPSULE G1 5000 Specimen No.:

T7C Test Temperature (F):

20 o

~.3000 Impact Energy (ft-lb):

6.5 3

~,

32000, General Yield Load, PGY (1b):

1 1000 i

Maximum Load, P ax (1b):

3400 0 0 1000 2000 3000 4000 5000 Time, psec i

5000 Specimen No.:

T51' 4000 i

Test Temperature (F):

25

/,

e 3000 Impact Energy (f t-Ib):

20.0 i

General Yield Lond, PGY (1b):

3400 1000 4050

-o Maximtat Lond, Pmax (1b):

o-8000 2000 3000 4000 5000 Time.psec

?

l Specimen Eo.-

T62 5000 4000 3000[

Test Temperature (F):

75 Impact Energy (f t-lb):

34.5 2

3 2000 Cencral Yield Load, PCY (1b):

3000 Maximum Load, P (1b):

4100 l

0 0 1000 2000 3000 4000 5000 Time, psec Specimen Uo.:

T65 5000 Test Temperature (F):

00 4000 8

Impact Energy (ft-lb):

43.0 3000 3050

$2000

~

General Yic1d Load, Pg,(Ib):

4050 1000 Maximum Load, Pmax (Ib):

00 1000 2000 3000 4000 5000 Time,psec i

I A-14 l

i TABLE A-4. (Continued)

I Specimen No.:

T7A 5000 M

Test Temperature (F):

130 3000 Impact Energy (ft-lb):

46.5 t

General Yield Load, Pg7 (lb): '2750

\\

1000 11aximum Load, P,g (1b):

3700

(

0 1000 2000 3000 4000 5000 Time, pec Specimen No.:

T6A 5000 Icst Temperature (F):

295 4000 e

O Impact Energy (f t-lb):

90.0

,3000 General Yic1d Load, P W:

2600 SM g7 1000 Mc::imten Load, P ax (1b):

3650 0

1000 2000 3000 4000 5000 Time, pec Specimen No.:

T6T 5000 4000 Test Temperature (F):

340

- p g

32000[

\\

Impact Energy (ft-Ib):

G3.5 Ceneral Yield Load, Pg7 (1b):

2600

\\

Hn:: intra Load, P (lb):

3700 0 0 1000 2000 3000 4000 5000 Time, pec

.=.,=---,,n_

b I

~

I

A-15 TABLE A-5.

IRSIRIEIENIED ClhKPY IMPACT DATA FOR QUAD CITIES UEIT NO. 2 ESU 1 AZ METAL FROM CAPSULE G2 Specimen No.:

L:X 5000 Test Temperature (F) :

_30 4000 f

a Impact Energy (f t-Ib):

36.5

,, M

$2000

{

General Yield Load, PGY (1b):

,3200 1000 Maximum Load, P,x (1b):

4100 0 0 ICD 0 2000 3000 4000 5000 i

Time,psac t

i Specimen No.:

HH 5000 Test Temperature (F):

-20 4000 f

e 3000-Impact Energy (f t-lb):

75.5 E' 2000 General Yield Load, PO,(lb):

3100 1000 l

Maximum Load, P (Ib):

4250 0

1000 2000 3000 4000 5000 Time, psec

?

Specimen No.:

22 5000 L

4000 f

Test Temperature (F):

-10

/

1

.o Impact Energy (f t-lb):

54.0

.3000 32000 3300 Cencral Yield Load, Pg. (1b)

1000 4350 Ilar:imtmi Load, Pmax (lb):

o u

O 1000 2000 3000 4000 5000 Time, psec 5000 TF2 Specimen 1:o.:

4000

!l '

20 2

Test Temperature (F):

3000 I

74.0 32000' Impact Enctgy (ft-lb):

3000 1000 General Yield Load, PGY (1b):

Q l

11n::imum Load, P (Ib):

0 1000 2000 3000 4000 5000 4150 0

Time.psec I

l

i A-16 f

TABLE A-5 (Continued) i Specimen No.:

n13 5000 l

4000 l

Test Temperature (F):

78

--3\\

.3000 Impact Energy (f t-lb):

114.0 r

(

0 General Yield Load, PGY ( ):,2800

\\

1000 Maximum Load, P, (1b):

3950

'N 7

0 1000 2000 3000 4000 5000-

[

Time, psac 4

^

Specimen No.:

HIP 5000 Test Temperature (F):

220 4000 3000;ln

=

Impact Energy (f t-lb):

120.0

\\

3 2000' General Yield Load, Pgy (1b):

2500 g

1000 Maximum Load, P (1b):

3600

\\

0 1000 2000 3000 4000.5000 7

Time psec Specimen No.:

Td5 5000 l

Te::t Temperature (F):

295 4000 a

.3000.f)

Impact Energy (f t-lb):

94.0 o

u General Yield Load, Pg (1b):

2500 3 2000 1000 j

Ma::Imum Load, Pmax (1b):

3500 s

u 0

500 1000 M oi 2000 2500 l

Time, psec m __

.m_..-

i I

i s

i e

k

I t

A-17 TABLE A-6.

INSTRUMENTED CFa'aPY DIPACT DATA FOR QUAD CITIES Uli1T E0. 2 ESW IE2 METAL FRO:1 CAPSULE G1 Specimen No.:

die 5000 I

Test Temperature (F):

-30 4000 f i

Impact Energy (f t-lb):

14.5 3000 I

General Yield Load, Pg (1b):

• 3400 3 2000 1000 Maximum Load, P (1b):

3800 O

1000 2000 3000 4000 5000 Time,psec Specimen Ko.:

HtY 5000 4000 Test Terperature (F):

-10

{.3000[

Impact Energy (f t-lb):

20.5 3400 3 2000 General Yield Load, Pg. (1b):

1000 4100 t

Maximc1 Load, Ptaan (1b):

00 1000 2000 3000 -4000 b000 Time, psec Specimen Mo.:

n:C 5000 4000 Ter,t Tenperature (F):

20 Impac t Lnergy (f t-lb):

66.0 h'3#

0 2000 Cencral Yield Load, Pg7 (1b):

3200 1000 Ma>:inum Lord, P ax (1b):

430C l

l 0

1000 2000 3000 4000 5000 Time, psec Specinen Ko.:

TML 5000 4000 Test Temperature (F):

35 3000 It: pact 1:ncrgy (f t-Ib):

42.0 3 2000 Cener:1 Yield Load, PO, (Ib):

3250 l

1000 4400 Maxinum Lord, Pnax (1b):

o x,

0 1000 2000 3000 4000 5000

[

Time, pse:

i i

I A-18

-l TABLE A-6 (Continued)

Specimen No.:

2 16 5000 Test Temperature (F):

78 4000 3

Impact Energy (f t-lb):

82.0

- 3000 g@

32 General Yic1d Load, Pg (1b):

3000 k

1000 Maximum Load, P (1b):

4250

(

0 0 1000 2000 3000 4000 5000 Time, psec i

Specimen Ilo.:

DID 5000 b I'

Tes t Temperature (F):

78 4000 Inpact Energy (f t-lb):

112.0

.W I

g 3000 32000 General Yic1d Load, Pg (1b):

\\

I#

Qi 4250 N

11a::imum 1.oad, Pna.. (1b):

o a

0 3(D0 2000 3000 4000 5000 Time psec i

t Spccinen 1:o.:

TLT 5000 4W Test Tc:uperature (F):

295 D

^

Inpact Encray (f t-lb):

133.5 E3#

General Yield Load, Pg (1b):

2450

'(

i Manime Load, P (Ib):

3650

.}-

0 f.00 1000. 1500 2000 2500 Time, psec I

O A-19 l

I TABLE A-7.

INSTRUMENTED CHARPY IMPACT DATA FOR i

QUAD CITIES UEIT EO. 2 I

SAW UELD NETAL FROM CAPSULE G1 i

t Specimen No.:

U4P 5000

-g i

Test Temperature (F):

78 4000 f

e Impact Energy (f t-lb):

12.0 3000 j

g General Yield Load, Pg7 (1b):

,3200 32000-i 1000 Manimum Load, P (Ib):

3650 00 1000 2000 3000 4000 ' 5000 Time, psec t

5000 Specimen No.:

U4C 4000 Test Temperature (F):

150 A

,3000 g

Impact Energy (f t-lb):

24.5 "32000 i

General Yield Load, Pg7 (Ib)-

2900 1000

(

i Maximten Load, Pmax (Ib):

3600 C

0 0 1000 2000 3000 4000 5000 Time,psec i

e 5000r l

Specimen No. :

U3U l

4000 Test Temperature (F):

150 g

Impact Energy (f t-Ib):

24.5 (3000, 0 2000' General Yield Load, P (1b):

3050

(

naxinue Load, P (1b):

3S00

(

O 1000 2000 3000 4000 5000

~

Time, psec l

Specimen No.:

U4A 5000 4000 l

Test Temperature (F):

220 e 3coch Impact Energy (ft-lb):

29.0 3'

j (

" 2000' a

Cencral Yic1d Load, Pg. (1b):

3000

\\

j 1000 t

naximum Lond, P 3x(1b):

3509

\\w 0

1000 2000 3000 4000 $000 i

Time,psec

?

e

i

?

A-20 i

TABLE A-7 (Continued) j i

Specimen No.:

U4g 5000 40 %

Test Temperature (F):

295 f

h3000(O l

Irepset Energy (f t-lb):

43.0

'.i2000 General Yic1d Load, Pgy (1b):

2800

(

1000 Maximum Load, P, (1b):

3500

\\

i 0

1000 2000 3000 4000 5000 Time, psec i

5000 U3D Specimen Eo.:

4000 Test Temperature (F):

295 p'\\

,,000

.o y

Impact Energy (ft-lb):

51.0 2700

\\

General Yic1d Load, Pg7 (Ib):

3500

(_

Haximum Load, Pmax (Ib):

0 0 1000 2000 3000 4000 5000 Time, pse:

3 4

i

?

i

+

r A-21 i

TABLE A-8.

INSIRUIID!TED CEJtPY IMPACT DATA FOR

+

QUAD CITIES UNIT E0._2 SAW IRZ METAL FRG1 CAPSULE G1 I

Specimen No.:

U6E

$000 Test Temperature (F):

-30 4000 a

t o

Impact Energy (f t-lb):

11.0

}3000 3 2000 General Yield Load, Pg (1b):

1000 Maximum Load, P (1b):

3450 0

1000 2000 3000 4000 5000-f 0

Time,psec j

5000 Specimen !!o.:

UCA 4000 Test Temperature (F):

-10 f

f 3000 Impact Energy (f t-lb):

12.0

=~

8' 2000 General Yield Load, PGY (1b):

3000 Maxinica Load, Pmax (1b):

3700 0 0 1000 2000 3000 4000 5000 Time, psec Speci:acn No. :

UCD 5000 l

Test Temperature (F):

20 4000 [

8 Impact Energy (it-lb):

50.0 3000 3300

$2000 General Yield Load, Pg (ib):

4250 IMO Ha:imum Load, Pmax (1b):

\\

0 1000 2000 3000 4000 5000 Tima, pes Speci:acn No.:

UAy,.

5000 4000 Test Temperature (F):

73 Impaet Energy (f t-Ib):

39.5 m'

j General Yic1d Load, P W:

3300 gy 1000 Ilaximun Load, P (Ib):

4000

\\

0 1000 2000 3000 4000 5000 Time, psec

A-22 l

TABLE A-8 (Continued)

Specimen No.:

U6K

$opo Test Temperature (F):

295 4000 o

u'

^

impact Energy (f t-lb):

62.5 3000 General Yield Load, Pg,(1b):

,2550 3 2000 Maxiraum Load, Pmax (1b):

3350 1000 y

0 t

0 1000 2000 3000 4000 5000 Time.pec Specimen No. :

U7P 5000 4000 Tes t Temperature (F):

295 8 3000 ^

Impac t Energy (f t-lb):

67.5 i32000[ }

General Yield Load, PGY (Ib):

2600

\\

1000 s

llaximen Load, P (Ib):

3450 N

O 1000 2000 3000 4000 5000 Time, pec i

)

=

h p

t i

A-23 Fracture Load-displacement Raw Remarks type curves data O

I P,

Brittle fracture 3

r r

3 1

Deft--ti.,n II e#

e B

P Brittle fracture s

GY c

s e*

+

De flection III E

P Brittle fracture followed by c

GY s

f racture indicative of shear lip formation Deflection

]

Stable crack propagation i

r IV

=

P followed by unstable brittle G1,'

r-e fracturs and'fractur6 p

max indicative of shear lip f r ati n-DeMection i

V

~p P

Stable crack propagation gy' e

followed by fracture p

ma::

indicative of shear lip formation Deflection V!

P t ble crack propagation s

CY' E,

followed by gross deformation p

~

m3X Deflection FIGU?I A-4 THE SIX TYPES OF FP.A" TUT 2 FOR NOTCFED DAR BENDING

i t

i A-24 r

i The pertinent data used in the analysis of each record are the general

( max), an fracture 1 ad (P ). 1 The impact yield load (PGY ' ""* ""*

p energy values listed in the tables are those normally obtained from the impact machine dial, j

The Charpy energy curves and the load-temperature information 3

?

obtained from the instrumented Charpy tests are shown in Figures A-5 through.

j A-9.

In general, the curves shpw both the general yield load and the

[

maximum load initially increasing as temperature is decreased from the j

upper shelf region of the Charpy impact curve. As temperature is further decreased through the transition temperature region, the maximum load goes through a maximum and drops off as temperature continues to be decreased.

The general yield load is also quite sensitive with respect to temperature.

As the temperature is decreased from the upper shelf region, the general yield load increases subs.tantially, j

The effect of irradiation can be seen in Figure A-5 (base metal),

t Figure A-6 (ESW weld metal), and Figure A-7 (ESU IIAZ metal). Specimens a

from these materials were irradiated in both Capsule G2 which had an 1

average fluence of 1.8 x 10 n/cm

(>l MeV) and in Capsule G1 which had

[

16 an averase fluence of 1.3 x 1019'n/cm2 (>l MeV). The Capsule G2 specimen i

i behavior is very close to unirradiated specimen behavior,(9) llowever, the l

t relatively high fluence Capsule G1 specimen behavior is appreciably shif ted by irradiation.

The b: pact energy versus temperature plots in Figures A-5, A-6, and A-7 show the curve is shif ted to higher temperature, and the upper shelf energy is decreased. The load versus. time plots in the same three figures show that in general both the general yield load and the maximum load curves have also shif ted to higher temperatures.

{

i 1

amu

L, A-25 Si 4500 3

,4 s

.)

P

/

s ma 4000

/

s s N t

h s4 3500

e ci g

i 33000

\\o o

p

]

GY s

\\

.}

3' d 2

2500

-O- -

-o-

- CAPSULE GI

-D--

2000

-O--

-A-

-CAPSULE G2 15 0 3'

-a--

3 3__g 12'5 f

'i

/

o-g f

- 100Z r

/

A 9

75 o{,

/

w l

a p

so

/

/

25 i

g l

I I

I I

'0-

- 10 0 0

10 0 -

200 300 Temperature, F l

r FIGlmE A-5.

INSTRi&!ENTED CFARPY LOAD-TDIPERATURE AND ENERGY--

TDIPERATURE CL'RVES FOR QUAD CITIES UNIT NO. 2 BASE METAL FRO'1 CAPSULES G2 cod G1 I

1

1 A-26 4500; i

i i

i i

4000 Pmax O

3500 O'

e i

A, o

" 3000 A

S a

PGY 2500 O O O CAPSULE GI 2000

- O 4 D CAPSULE G2 15 0 12 5 n

~

d y

100 g d-75 5 m

CW

- 50 O

O

.J 1

25 D$

'0

-10 0 0

100 200 300 Temperature, F TICURE A-6.

INSTRL"1ENTED CHARPY LOAD-TD1PERATL'RE AND 2:ERGY-TEIPDATl'RE C1'R"ES FOR QUAD CITIES UNIT 1:0. 2 ESW WELD METAL FRO'1 CAPSULES G2 and G1

A-27 4500 1

j 0

10 4000 P

max 3500 2

. :s I

A 3 3000 P

GY 2500 3

4-O O O CAPSULE GI 2000 - 0 A R CAPSULE G2 15 0 g

125 da 100 6 O

a

'G a ~

75 e O

t5

[O 50 25 i

+

~

~

i i

i i

0

-10 0 0

10 0 200 300 Temperature, F TICl:RE A-7.

IIISTRO1D4TED CIRRPY LOAD-TDIPERATURE AND E;ERGY-TDIPERATCRE CURVES FOR OUAD CITIES LTIT NO. 2 ESL! HAZ METAL FROM CAPSULES G2 and G1 i

i

A-28 4500-i i

4000 O

Pmax 3500 -

O d

a O

.3 3000 -

o P

gy 3

2500 2000 15 0 i

- 12 5 e

100 $-

i 75 a-t5 50 25 i

i i

i 0

-10 0 0

10 0 200 300 Temperature, F i'

FIGLTE A-S.

D;STR1DIEiTED CEARPY LOAD-TDIPERATURE AND EMERGY-TDiPDL\\TURE -

CURVES FOR QL'AD CITIES 103I7 KO. 2 SAW WELD METAL FRO:1-CAPSULE 01 J

l I

1 i

A-29 i

4500.

l r

4000<

P 1

mox 3500:-

e O

0 P

o GY 1

3 3000 l

2500:-

i i

2000; -

15 0 I

12 5 ly e

i I

8 100 = -

I s

5 en L

75 b W

5 i

0 50 r

l d

r 25 l

l t

i I

i g

-10 0 0

100 200 300 Temperature, F l

FICURE A-9.

INSTREIENTED CliARPY LOAD-TD;PERATURE AND INERGY-TDIPEPATLIE CURVES FOR Qt:AD CITIES IIIT KO. 2 SAW IRZ METAL FROM i

CAPSULE G1 t

y

-)

A-30 i

CONCTBSTONS l

The instrumented Charpy impact test technique was used to study

(

the impact behavior of pressure-vessel materials.

The maximum load was shown to go through a maximum as temperature is lowered from the upper shelf region into the transition temperature region.

In.eddition, the general

{

yield load was shown to increase as temperature is decreased.

i 8

E i

i P

l F

f i

h

]

h A-31

-f

?

I APPENDIX A REFERENCES i

(1) Wu11aert, R. A., Ireland, D. R., and Tetelman, A. S., " Radiation Effects on the Metallurgical Tracture Parameters and Fracture Toughness of Pressure Vessel Steels", paper presented at the ASTM Annual Meeting, Niagara Falls, New York, June 29, 1970.

,y (2) Wu11aert, R. A., " Applications of the Instrumented Charpy Impact l

Test", in Impact Testina 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.

21st Conference on Remote Systems Technology, American Nuclear Society (1973).

(4) Wilshaw, T. R., and Pratt, P.

O., "The Effect of Temperature and Strain Rate on the Defprmation and Fracture of Hild-Steel Charpy '

j Specimens", in Proceedings of the First International Conference on l

Fracture, Sendai, Japan, September,1965, 2, p 973.

(5) Tetelman, A. S., and McEvily, A. J. R., Fracture of S tructural Materials John Wiley and Sons, Inc., New York (1967).

(6) Knott, J. F., "Some Effects of Hydrostatic Tension on the Fracture Behavior of Mild Steel", Ph.D. dissertation, University of Cambridge, Cambridge, England (1962).

i (7) Fearnehough, C. D., and Hoy, C. J., " Mechanism of Deformation and j

Fracture in the Charpy Test as Revealed by Dynamic Recording of Impact Loads", Iron Steel Inst., 202, 912 (1964).

t (8) Server, W. L., and Tetelman, A. S., "The Use of Precracked Charpy Specimens to Determine Dynamic Fracture Toughness", UCLA-ENG-7153 (July, 1971).

(9) Perrin, J. S., and Lowry, L. M., " Quad Cities Uuclear Plant Unit No. I and Unit No. 2 Reactor Pressure Vessel Surveillance Programs:

}

Unirradiated Mechanical Properties", Final Report to Commonwealth Edison Company from Batte11c's Columbus Laboratories (February 15, 1975),

t

't

[

t

.