ML18043A800

Final Rept on Palisades Nuclear Plant Reactor Pressure Vessel Surveillance Program:Capsule A-240, by Battelle Columbus Labs

ML18043A800
Person / Time
Site:	Palisades
Issue date:	03/13/1979
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18043A798	List: ML18043A797 ML18043A799 ML18043A800
References
BCL-585-12, NUDOCS 7907120344
Download: ML18043A800 (95)

Text

-~~**

[_

r.

FINAL REPORT on PALISADES NUCLEAR PLANT REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM:

CAPSULE A-240 to CONSUMERS POWER COMPANY March 13, 1979 by J. S. Perrin, E. 0. Fromm, D. R. Farmelo, R. S. Denning, and R. G. Jung BATTELLE Columbus Laboratories 505 King Avenue Columbus, Ohio 43201 BCL-585-12

__ !. - --~- - -----

\\_..

I '*.

i L,

i '

r:

I

' i_

f--: L.

r--

L_.

r-*

SUMMARY

INTRODUCTION.

TABLE OF CONTENTS CAPSULE RECOVERY AND DISASSEMBLY SPECIMEN PREPARATION..

EXPERIMENTAL PROCEDURES.*

Neutron Dosimetry.

Thermal Monitors

• Charpy Impact Properties Tensile Properties RESULTS AND DISCUSSION...

Neutron Dosimetry.

Thermal Monitors

• Charpy Impact Properties Tensile Properties CONCLUSIONS.

REFERENCES.

APPENDIX A INSTRUMENTED CHARPY EXAMINATION.....

APPENDIX B 1

2 3

6 9

9

.ll

.12

.15

.18

.18

.28

• • 34

.47

.52

.53 A-+

COMPOSITIONAL ANALYSIS OF SURVEILLANCE TEST MATERIALS...... B-1 APPENDIX C IN-REACTOR LOCATION OF SURVEILLANCE CAPSULE ASSEMBLIES..... C-1

l.c L

I '

L_.

1-I""'

I L~.

/ -

LIST OF FIGURES FIGURE 1.

TYPICAL SURVEILLANCE CAPSULE..

FIGURE 2.

CHARPY V-NOTCH IMPACT SPECIMEN.*

FIGURE 3.

TENSILE SPECIMEN....

• * * *. 4 FIGURE 4.

INSTRUMENTED CHARPY MACHINE.

FIGURE 5.

LOAD TRAIN USED FOR DETERMINATION OF TENSILE PROPERTIES....**.**

FIGURE 6.

FIGURE 7.

CAPSULE A-240 DIAGRAM WITH FLUENCE (E>l MeV) RESULTS..........

DIAGRAM OF FLUX SPECTRUM AL'ID FLUX ATTENUATION HOUSINGS....*...

FIGURE 8.

PALISADES GEOMETRY USED IN DOT RUN.

FIGURE 9.

COMPARISON OF THE NEUTRON FISSION SPECTRUM WITH THE DOT CALCULATED SPECTRUM AT THE CAPSULE.

FIGURE lOA.THERMAL MONITORS FROM TOP TENSILE COMPARTMENT NO. 1614 *.....*...

FIGURE lOB.THERMAL MONITORS FROM MIDDLE TENSILE COMPARTMENT NO. 1641.......*.

FIGURE lOC.THERMAL MONITORS FROM BOTTOM TENSILE COMPARTMENT NO. 1673.........

FIGURE 11. CHARPY IMPACT PROPERTIES FOR BASE METAL, PLATE NO. D3803-l, LONGITUDINAL ORIENTATION.....

FIGURE 12. CHARPY IMPACT PROPERTIES FOR BASE METAL, PLATE NO. D3803-l, TRANSVERSE ORIENTATION....

FIGURE 13. CHARPY IMPACT PROPERTIES FOR WELD METAL..

FIGURE 14. CHARPY IMPACT PROPERTIES FOR HEAT AFFECTED ZONE METAL.. *... *..........

FIGURE 15. CHARPY IMPACT FRACTURE SURFACES FOR PALISADES CAPSULE A-240, BASE METAL LONGITUDINAL ORIENTATION.. *...... *.......

FIGURE 16. CHARPY IMPACT FRACTURE SURFACES FOR PALISADES CAPSULE A-240, BASE METAL TRANSVERSE ORIENTATION.

FIGURE 17. CHARPY IMPACT FRACTURE SURFACES FOR PALISADES

.7

• .8

.. 14 16 19

. 20 26 27 31 32 33

. 37

. 38 39 40 41 42 CAPSULE A-240, WELD METAL..........

. 43 FIGURE 18. CHARPY IMPACT FRACTURE SURFACES FOR PALISADES CAPSULE A-240, HAZ METAL.........

44 FIGURE 19. POSTTEST PHOTOGRAPHS OF PALISADES TENSILE SPECIMENS FROM CAPSULE A-240..

49 fIGURE 20. TYPICAL STRESS STRAIN CURVE...

51

r-I.

LIST OF TABLES TABLE 1.

INVENTORY OF MECHANICAL PROPERTY SPECIMENS REMOVED FROM CHARPY AND TENSILE COMPARTMENTS FROM PALISADES CAPSULE A-240.*.... * *...

TABLE 2.

FLUX SPECTRUM SET MATERIALS AND LOCATIONS.

TABLE 3.

DOSIMETER SAMPLES RECOVERED..

.5

• 9

. 11 TABLE 4.

THERMAL MONITOR COMPOSITION. *

• 12 TABLE 5

• CALIBRATION DATA FOR THE BCL HOT LABORATORY CHARPY IMPACT MACHINE USING AMMRC STANDARDIZED SPECIMENS.........

.. *.. 13 TABLE 6.

FAST NEUTRON DOSIMETRY RESULTS (E>l MeV)

FOR PALISADES **.*.*......

...... 21 TABLE 7.

CROSS SECTIONS FOR THE WIRE MONITORS (E>l. 0 MeV) IN NINE MESHES.....

TABLE 8.

CONSTANTS USED IN DOSIMETRY CALCULATIONS TABLE 9.

CHARPY V-NOTCH IMPACT RESULTS FOR PALISADES 29

. 30 BASE METAL, LONGITUDINAL ORIENTATION......... 35 TABLE 10. CHARPY V-NOTCH IMPACT RESULTS FOR PALISADES BASE METAL, TRANSVERSE ORIENTATION.........

• 35 TABLE 11. CHARPY V-NOTCH IMPACT RESULTS FOR PALISADES WELD METAL............. *......... 3 6 TABLE 12. CHARPY V-NOTCH IMPACT RESULTS FOR PALISADES HAZ METAL.

36 TABLE 13.

SUMMARY

OF CHARPY IMPACT PROPERTIES FOR PALISADES.

45 TABLE 14. 50 FT-LB AND 35-MIL LATERAL EXPANSION SHIFTS

.DUE TO IRRADIATION FOR PALISADES CAPSULE A-240.

46 TABLE 15. TENSILE TEST RESULTS FOR PALISADES CAPSULE A-240 48

l.-

r*

I I :

1__..:

I :

L.

n I '

'.}

r**

)

, ___ J

(.

\\ I

\\

I_.

FINAL REPORT on PALISADES NUCLEAR PLANT REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM:

CAPSULE A-240 to CONSUMERS POWER COMPANY from BATTELLE Columbus Laboratories March 13, 1979

SUMMARY

Capsule A-240 was removed from the Palisades Nuclear Power Plant after 2.26 equivalent full power years of reactor operation.

The capsule was sent to the Battelle Columbus Hot Laboratory for examination and evaluation.

The irradiation temperature did not exceed 536 F as indicated by the examination of the 12 thermal monitors.

The neutron fluence at the location of the specimens was determined to be 4.4 x 1019 nvt (E>l MeV),

using neutron dosimeters from within the capsule.

At the vessel wall the 19 2

maximum exposure was determined to be 3.2 x 10 n/cm at 32 full power years.

The radiation-induced changes in the mechanical properties of pressure vessel material specimens were determined.

Charpy impact specimens were used to determine changes in the impact behavior, including the shifts in the transition temperature region and the drops in the upper shelf energy level.

Evaluation of the tensile property specimens included the yield and ultimate strengths as well as elongation and reduction in area.

I I

L....:

i L_:

i i i i l~-..J r-: :-*

l 1**:

\\

I_

2 INTRODUCTION Irradiation of materials such as the pressure vessel steels used in reactors causes changes in the mechanical properties, including tensile, (1 6)*

impact, and fracture toughness.

Tensile properties generally show a decrease of both uniform elongation and reduction in area accompanied by an increase in yield strength and ultimate tensile strength with increasing 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.

Commercial nuclear power reactors are put into operation with reactor pressure vessel surveillance programs.

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

The surveillance program includes a determi-nation of both the preirradiation baseline mechanical properties and periodic determinations of the irradiated mechanical properties.

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

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

These capsules typically contain neutron flux monitors, thermal monitors, Charpy impact specimens, and. tensile specimens.

Capsule_s 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.

Palisades has a surveillance program which is described in a report issued by Combustion Engineering. (l).The program is based on ASTM El85 "Surveillance Tests on Structural Materials in Nuclear Reactors"(S), and is conducted using numerous other ASTM standards. C9)

At the time of initial ope-ration of the reactor, the pressure-temperature operating curve was specified.

During the life of the reactor, the curve is to be revised to account for the changes in the Charpy impact behavior of the vessel materials.

• References at end of text.

(-,

i l _*

\\ *.. 1

[

i l..-1 i _ _j

~*

l I-*

i L

3 A previous report covers the preirradiation base-line tensile and Charpy impact properties of four materials from Palisades(lO).

These materials include base metal both longitudinal and transverse orientation, weld metal, and heat affected zone (HAZ) metal.

The present report describes the results obtained from examination of capsule A-240 which was removed from the reactor during January, 1978.

CAPSULE RECOVERY AND DISASSEMBLY A Battelle shipping cask BMI-1 was sent to the reactor site to pick up the capsule which had previously been prepared for loading and was stored in the spent fuel storage pool.

Reactor personnel loaded the Palisades capsule A-240 into the shipping cask and the cask was then shipped from the reactor site to the BCL Hot Laboratory for postirradiation examination.

Upon arrival at BCt, the capsule assembly was removed from the cask and transferred to a hot cell for visual observation, photography, and disassembly.

Visual examination showed no unusual features or damage.

Figure 1 shows a sketch of a typical surveillance capsule from Palisades.

The capsule compartments were cut apart using a flexible abrasive wheel attached to a Mototool.

The capsule contained four Charpy compartments and three tensile compartments.

The identification numbers of these compart-ments are as follows, with the first being located at the top end of the capsule and the last being located at the bottom end of* the capsule assembly.

1614 Tensile, thermal monitor, and dosimeter compartment 1624 Charpy compartment 1632 Charpy compartment 1641 Tensile, thermal monitor, and dosimeter compartment 1651 Charpy compartment 1663 Charpy compartment 1673 Tensile, thermal monitor, and dosimeter compartment Each tensile compartment contained three tensile specimens, a set of 7 flux spectrum monitors, a set of 5 flux attenuation monitors, and a set of 4 thermal monitors.

Each Charpy compartment contained 12 Charpy specimens.

An inventory of the mechanical property specimens from the capsule is listed in Table 1.

r:

i I :

L._,

,~

L:

j r1 l~_;

p I [._;

4 TENSILE-THERMAL MONITOR CHARPY IMPACT CO~PAR_TMENTS 1-;

lJ TENSILE-THERMAL-MONITOR I '

i.__:

r...

L_.,

-1,

l -

( -*,

i I

l...

AND DOSIMETER COMPARTMENT TENSILE-THERMAL MONITOR

, AND DOSIMETER COMPARTMENT.

CHARPY IMPACT COMPARTMENTS FIGURE 1.

TYPICAL SURVEILLANCE CAPSULE

L (.

I i

_ j I

l_'

L...

r-,

\\

r ! '.

L.>

r-~-

1 l_j i

(__.

c**-

1 -

I.

\\.......

i -

5 TABLE 1.

INVENTORY OF MECHANICAL PROPERTY SPECIMENS REMOVED FROM CHARPY AND TENSILE COMPARTMENTS FROM PALISADES CAPSULE A-240 Compartment Material No.

Type Specimen Identification CharEY ComEartments 1624 HAZ 41T 45T 43T 46T 42T 44U 43U 45U 42U 41U 1632 Base Transverse 235 232 237 23A 236 234 231 22U 233 22P 1651 Base Longitudinal 124 123 12A 126 120 121 122 llP 127 llT 1663 Weld 332 32P 31C 32T 335 32U 331 32E 31K 31J Tensile Compartments 1614 HAZ 4D4 4D7 4D5 1641 Base Longitudinal 1D4 lDl 1D5 1673 Weld 3DA 3DB 3D7 44T 46U 22Y 22T 12B 125 311 327

\\

I

\\ '

\\

I r **.

l

~-_;

6 SPECIMEN PREPARATION The base metal of the reactor pressure vessel is SA-302 Grade B.

Mechanical property specimens were prepared from actual vessel plate in accordance with CE specifications and provided to Consumers Power.(?)

All specimens were made from flat slabs taken parallel to the plate surfaces and at the 1/4 plate thickness.

Longitudinal base metal Charpy and tensile specimens were oriented with the major axis of the specimen parallel to the principal rolling direction of the plate and parallel to the surface of the plate.

Transverse base metal Charpy specimens were oriented with the major axis of the specimen perpendicular to the principal rolling direction and parallel to the surface of the plate.

Longitudinal weld metal Charpy and tensile specimens were oriented with the major axis of the specimen parallel to the direction of the weld and parallel to the surface of the weld.

Heat-affected-zone specimens were oriented with the major axis of the specimen perpendicular to the direction of the weld and parallel to the surface of the weld.

The axis of the notch of all base metal and weld metal Charpy impact specimens was perpendicular to the surface of the plate or weld.

The axis of the notch of all heat-affected-zone Charpy impact specimens was parallel to the surface of the plate.

Compositional analyses of the materials used in fabrication of the specimens are tabulated in Appendix B.

The Charpy impact specimen is shown in Figure 2 and is the standard specimen recommended in ASTM E23-72. (ll)

The tensile specimen design is shown in Figure 3.

It has a nominal 0.250-in. gage diameter and a nominal 1.00-in.

gage length

• PUNCH MARK

£ND j-1.oazt.005 I

SC£ NOT£4 I I

,,1 I:

90°+/-0°/0'

.... 1--------2165-::gg:§ ~

450;!: Jo ZZ 030'-.!:.0° 30' BLANK IDNTIF/CllTION END

.8/5t.OOJ

J r=r I

t

~

_.;;;C;..:._H_fl;..:._R;..:_P.....:..Y--'-1 ;_;.M_:_P:;_:_'A_;:__CT:___;S=R-='E=C~J M~£=N-=-

. Ef

,394:t.001-l-J

?.q_u_A~f..

.01ot.001 ~

TYPE A DETAIL Z SEE NOT£ 4 5Cf/L£: 4:1 FIGURE 2. CHARPY V-NOTCH IMPACT SPECIMEN

-. i G. /00%' DI.MENS/ON. INSPECTION REQUIRE

5. A£ MOVE. ALL BURR 5

4. MILL OR BROACH "V" NOTCI-/.

OR TOOL MARKS PERMITTED.

NOTCH Mll.5 BE LOCATED FROM PUNCH MARI~ E:.ND.

NOTCH TO BC ORIENTED AS SHOWN WITH IDENTIFICATJON MARKING IN UPRIGHT POSITION

3. STAMP THIS £ND AFT£.R M,l\\Cl-l/NJN6 WITH.SAMC ID£NTIFICATJON ANP SAME ORl£NT/\\TION FOLLOWED 13Y A, PVNCI-/ MARK.

USE LOW STRE.$$ STAMP.

~.NOTE: JND£'NTIFICATION ON 8LANK AND RESTAMP 5P£C1Mt:N ON.SAME: [ND JN SAME OR/£NTATION AFTER MAC~-llNING.

us£ LOW 5TRE.SS STAMP

~..

J, FINISJ-1 GRIND ALL 5URFAC£S EXCEPT V GROOVE TO 32 RMS OR BETTER WHILE.

MAINTAIN ING CONTINUOUS FLOW or COOLANT.

CENTERS PERMISSllBLf

. TYP

°kDl/1 MRX

!,_.* _ - l

(.

<l+ I

---

.J-~--------11-t PUNCH MARK

?ND ij REF. REDUCED SECTION FIGURE 3.

TENSILE SPECIMEN l...... J

.!._X"15*CHAM

32. TYP.

. -BLANK IDENTIFICATION fND

{z.-14 UNC-2 /l lIAl.002 m~I TYP

(---- --.

L ---- 1...--* -~

L....... :

c.. *:.J

.--*-*** ""'1

~.

• G. I007o D/M£NSIONAL INSPCCTION REQUIRED.

S. STAMP OPPDSITC LND /\\FTf.R MACHINING-WITH SAME ID£NTIFICAT/ON FOl.LDIVED BY A PVNCH MARK,. USE LOW STRESS STAMP.

"'I, NOTE ID£NTIFJCATIOIV ON 8LANI<

AND RESTAMP SPtCIMEN ON SAME" END AFTER hll\\CHININ6

3. POLISH REDUCE.D S£CTION ~ ~nDIUS T032 RMS ll\\' BfTT£R-R£M111NDER llS MRCHINE'D.

Z. D 1*f1CTUAL *o* D//lMETER+.OOZTOt.0051 AT END5 OF REDUCED 5£CTION D£CR£11S/NG flND BLE.llD.:D TO *0*11rc£NTt:fJ

/. D"",zso I.DOI DllJ /IT CENTER I OF REDUCED SECTION 00

I ! :

L.

l.*

9 EXPERIMENTAL PROCEDURES This section describes the experimental procedures used in the examination of the thermal monitors, the determination of the neutron exposure, and the determination of the Charpy impact and tensile properties.

All testing was conducted at Battelle's Columbus Laboratories according to applicable ASTM procedures.

The data for the program are recorded in BCL Laboratory Record Books 34077 and 33015.

Neutron Dosimetry Two sets of flux monitors were recovered from three axial locations as described in capsule disassembly.

One set of flux monitors, identified as the fllL~ spectrum set, consists of six different materials in seven locations.

The material, locations, reactions, and product half-lives are shown in Table 2.

TABLE 2.

FLUX SPECTRUM SET MATERIALS AND LOCATIONS.

L (1) ocation Product.

in Set Material Reaction Half-Life 1 5 C2)

Uranium U238(n,F)Csl37 30.0 y 2

Titanium T.46(

)S 46

l.

n,p c

83.8 d 3

Iron Fe54(n,p)Mn54 314 d 4

Sulfur S32(n,p)P32 14.3 d 6 (2)

Nickel N"58 (

)C 58

l.

n,p o

71.3 d

/2)

Copper 63 60 Cu (n,a.)Co 5.26 y (1)

Position number or number of grooves in stainless steel sheath.

(2)

Cadmium covered.

The materials were encapsulated in 1/8 in. stainless steel sheaths, except for sulfur which was contained in quartz.

These are described in Combustion Engineering Report No. P-NLM-019(7), Figures 11, 12, and 13.

10 The flux attenuation set is composed of iron wires in 1/16 in.

stainless steel sheaths and is used to measure the flux attenuation through the thickness of a Charpy specimen.

The first three positions are in the center of the holder, No. 4 is toward the core side and No. 5 is closer to the vessel side as shown in Figures 11 and 14 of Reference (7) and Figure 7 in the present report.

All 36 dosimeter sheaths (7 spectrum x 3 locations plus 5 attenu-ation x 3 locations) were recovered, identified, and transferred to the radio-chemistry laboratory.

They were then opened with a minitubing cutter, and the sample was placed in a clean marked vial.

At this point some problems were encountered in that the six uranium samples, expected to be metal form from Reference No. (7)were found to be a fine powder.

The cadmium-covered uranium samples were of little value due to adherence of fine powder to the cadmium metal.

Cadmium has a melting point of 610 F and is not recommended for use over about 400 F due to its softness and ability to flow or distort.

The two copper wires had a silvery appearance as :i,,f they had reacted with the cadmium.

There was no copper sample in Capsule 1641, Position No. 7.

Apparently an error was made during assembly, since the sheath was marked with 5 grooves, and the uranium sample with 5 grooves had already been recovered.

Several iron wires were highly oxidized and difficult to clean.

Two out of three titanium wires were unsatisfactory for analysis.

They were copper colored, very brittle, and in several pieces.

It is believed they may have formed titanium nitride by reacting with the environment at elevated temperatures over a long period of time.

Table 3 is an inventory of samples recovered from each compartment including their form, and condition.

Summarizing, Fe wires from all 15 attenuation set locations were cleaned, weighed, and counted.

Similarly, from the spectrum set, 3 Fe samples, 3 Ni, 2 Cu, and 1 Ti sample. were analyzed.

Mr. Rolfe Jenkins of Consumers Power agreed(a) that a sufficient number of good data points were available, and that analyzing the uranium powder samples to the desired accuracy would not be possible.

It was mutually decided that the 14.3 d P-32 activation product of irradiated sulfur would be a meaningless number.

(a) Meeting at BCL November 21, 1978.

I.

I 1-*

I.

I I

i.

I L-Capsule 1614 1641 1673 1614 1641 1673 Set At ten.

At ten.

At ten.

Spectrum Spectrum Spectrum 11 TABLE 3.

DOSIMETER SAMPLES RECOVERED No. of Wires/Position or Number of Grooves 1

3 Fe 3 Fe 3 Fe oxidized u

powder u

powder u

powder 2

3 Fe 3 Fe 3 Fe oxidized pcs of Ti 3

3 Fe 3 Fe 3 Fe oxidized 5 Fe pcs of 5 Fe Ti 2 broken 5 Fe Ti wires 4

3 Fe 3 Fe 3 Fe oxidized S in quartz S in quartz S in quartz 5

3 Fe 3 Fe 3 Fe oxidized Cd covered U powder Cd covered U powder Cd covered U powder 6

7 1 Ni 1 Cu 1 Ni 5 grooves no sample 1 Ni 1 Cu The four activation products Mn-54, Co-58, Co-60, and Sc-46 from the nine samples were quantitatively analyzed utilizing a 50 cc lithium drifted-germanium (GeLi) solid state detector, capable of 2.7 KeV resolution(b),

in conjunction with an Ortec Model 6240 Multichannel Analyzer.

Theoretical counting efficiency curves were prepared from National Bureau of Standards, Standard Reference Materials (SRM).

The procedures used in the dosimetry sample evaluation followed the appropriate ASTM recommendations(l2-l6).

An explanation of the fluence determination is described under Neutron Dosimetry in the Results and Discussion Section.

Thermal Monitors The capsule contained four kinds of low-melting-point alloy wires for determination of* the maximum temperature attained by the test specimens during the irradiation period.

A typical thermal monitor consisted of a helix of wire of a particular alloy composition located below a stainless steel (b)

Full width-half maximum (FWHM) at 1332 KeV Co-&o peak.

i '

L.c*

i--

1.

i"'

I

~~-

I 12 weight inside a quartz tube.

Identification of a specific type of thermal monitor was by measurement of the overall length of the quartz tubing.

The identification of each of the four alloys in a given thermal monitor compart-ment is given in Table 4.

TABLE 4.

THERMAL MONITOR COMPOSITION Length of Quartz Composition of the Melting Point, Capsule, in.

Alloy, percent F

1 92.5 Pb, 5.0 Sn, 2.5 Ag 536 1-1/4 90.0 Pb, 5.0 Sn, 5.0 Ag 558 1-:-1/2 97.5 Pb, 2.5 Ag 580 1-3/4 97.5 Pb, 0.75 Sn, 1. 75 Ag 590 The four thermal monitors as indicated in Table 4 were located in each of three tensile, thermal monitor dosimeter compartments, having identifications 1614, 1641, and 1673.

During capsule disassembly, the four thermal monitors were recovered from each of the three compartments and were examined for evidence of melting using a stereomicroscope at a magnification of about 4X.

Charpy Impact Properties The Charpy impact tests were conducted using a 240 ft-lb Satec-Baldwin MODEL Si-lC impact machine in accordance with ASTM E23-72. (ll)

The 240 ft-lb range was used for all tests.

The velocity of the hammer at impact was 16.95 ft/sec.

The calibration of the machine was verified as specified in ASTM E23-72 and proof tested using standardized Charpy impact specimens purchased from the U.S. Army Materials Research Agency (AMMRC).

The results of the proof tests are listed in Table 5.

1-:

I r.

i I.

\\,

i.

13 TABLE 5.

CALIBRATION DATA FOR THE BCL HOT LABORATORY CHARPY IMPACT MACHINE USING Al.'1MRC STANDARDIZED SPECIMENS AMMRC Average Standard Variation BCL Energy, Energy(a),

Group Ft-Lb Ft-Lb Actual Allowed Low Energy 13.7 13.5

+o. 2 ft-lb

+/-10 ft-lb Med:Lum Energy 47.0 49.2

-4.4 percent

+/-5.0 percent High Energy 73.1 73.0

+o.l percent 5.0 percent (a) Established by U.S. Army Materials and Mechanics Research Center.

The instrumented Charpy impact machine is shown in Figure 4.

The Dynamic Response Module associated with the instrumented Charpy testing is mounted on top of the impact machine.

The digital oscilloscope located to the right of the machine is used to digitize and record load-time d d (l?)

Th d

1 t d t th data generate uring impact tests.

e x-y recor er oca e o

e right of the digital oscilloscope is used to produce x-y plots of the load-time curves.

ASTM procedures for specimen temperature control were utilized.

The low-temperature 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 inch from the bottom.

The height of the bath was enough to keep a minimum of 1 inch of liquid over the specimens.

The Charpy specimens were held at temperature for a minimum of at least the ASTM recommended time.

~*

I l i

(.

FIGURE 4.

INSTRUMENTED CHARPY MACHINE The Dynamic Response Module is shown mounted on top of the Charpy impact machine, and the digital oscilloscope and XY recorder are shown to the right of the Charpy impact machine.

. \\ **

I 15 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 80 F was oil.

The specimens were manually transferred from each temperature bath to the anvil of the impact machine by means of tongs that had also been brought to temperature in the bath.

The specimens were removed from the bath and impacted in less than 5 sec.

The energy required to break the specimens was 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 obtained from 3X photographs of the fracture surfaces by measuring the shear area using a planimeter and comparing this with the total fracture area. (l3)

Tensile Properties The tensile tests were conducted on a screw-driven Instron testing machine having a 20,000-lb capability.

Crosshead speeds of 0.005 and 0.05 inch per minute were used.

The deformation of the specimen was measured to a point just beyond the maximum load by using a strain gage extensometer.

Deformation beyond the maximum load was measured using t he crosshead speed (0.05 in./min) and the elapsed time.

The strain gage unit senses the diff erential movement of two extensometer extension arms attached to the specimen gage length 1 inch apart.

The extension arms are required for thermal protection of the strain gage unit during elevated temperature tests.

Figure 5 shows the extensometer extension arms and strain gage assembly used for tensile testing.

The strain gage unit is shown at the bottom left of the figure next to the region of the extensometer arms where the unit is attached during testing.

The extensometer was calibrated before testing using an Instron high-magnification drum-type extensometer calibrator.

The irradiated tensile specimens were tested at room temperature, 535 F and 550 F.

Elevated temperature tensile tests were conducted using a hot air-furnace.

The specimens were held at the temperature for 20 minutes before testing as required by ASTM.

Specimen temperature was monitored using Chromel-Alumel thermocouples attached directly to the specimen within the gage section of the specimen.

Temperature was controlled within +/-5 F throughout the 20 minute soak period as well as for the actual tensile test.

(.

I l.

KNIFE EDGE-~

EXTENSOMETER EXTENSION-ARM-~

CLIP GAGE----~

4752 FIGURE 5.

LOAD TRAIN USED FOR DETERMINATION OF TENSILE PROPERTIES Specimen is located under extensometer knife edges in center of photograph.

Clip-on strain gage attached to ex tensometer arms is shown in lower region of photograph

• I

(.

r i

re c -i.

t

(.

l 1

=*

I I

17 The load-extension data were recorded on the testing machine strip chart.

The yield strength, ultimate tensile strength, uniform elongation, and total elongation were determined from these charts.

The reduction in area was determined from specimen measurements made using a blade micrometer.

The total elongation was determined from the increase in distance between two punch marks which were installed 1 inch apart on the gage length prior to testing.

i.

\\ *... -'

i l. -~

i.

L.1

)

(_:

[l r-,

I

~*

I.

I I.._.

(

) '

\\

I

~. '.

'* l 18 RESULTS AND DISCUSSION Neutron Dosimetry The surveillance capsule was in the reactor for 825.08 equivalent full power days or 2.26 equivalent full power years (based on a reactor full power of 2540 MWt). (l9)

The capsule was located at a core position of 240 degrees(l9) and was in contact with the outer surface of the core support barrel, reference Figure C-1, Appendix C.

The capsule contained three flux monitor compartments which were located near top, near middle, and near bottom of the capsule as shown in Figure 6.

Each compartment contained a flux attenuation set of monitors at the top and a flux spectrum set of monitors near the center [Figures 11 and 14 of Reference (7)].

Figure 7 shows the physical dimensions of the monitor housing (20) which fit inside the capsule The capsule is basically a 3/4 in. by 1-1/2 in.

tube.

Figure 7 also shows the position of the iron, nickel'. copper, and titanium wire monitors which were irradiated in the flux spectrum sets and shows the positions of the iron wires which were irradiated in the attenuation sets.

The wire monitors were counted for activation product gamma ray activity to determine the fast fluence at each monitor.

The results are shown in Table 6.

The results for iron wires 1, 2, and. 3 of the attenuation set show that the change of fluence in the circumferential direction is small over the capsule dimensions.

Therefore, a good fluence measurement at each of the capsule locations is the average of the fluences of the iron wire in the fluence set and iron wires 1, 2, and 3 of the attenuation set (since these are also at the radial center of the capsule).

These results are shown in Table 6 and in Figure 6 under the heading Fe (avg).

Because the nuclear constants of iron are well established, this value of fluence at each of the compartments is considered to be the best value.

The nickel results should be disregarded because the half-life of the Co-58 acti-vation product is only 71.3 days and its result tends to reflect the flux level near the end of the cycle.

The Sc-46 activation product of titanium also has a short half-life of only 83.8 days.

Copper results are slightly higher although results agree well with the iron values.

The average result in the capsule, as given by the average of the iron results in the three compartments, is 4.42 x 1019 n/cm2 at the capsule center line.

Values range from 4.26 x 1019 in the top to 4.60 x 1019 in the bottom compartment which is less than ten percent change over the length of the capsule.

i ;

.. U

• ~

i I.

. L

~.

NUMBER 1614 r

TENSILE-THERMAL MONITOR L.J AND DOSIMETER CO~PA~TME_N_r r:

t_.1 u

. T1

{_.~;

~--\\

1*

(-*

J.

\\.. *

\\

)

I

l.

i.

l

\\

NUMBER 1641 TENSILE-THERMAL MONITOR AND DOSIMETER COMPARTMENT I

I NUMBER 1673 TENSILE-THERMAL MONITOR AND DOSIMETER COMPARTMENT 19 1_.__ ___ 4.3 x 1019 NVT (avg) l CHAR PY IMPACT COMPARTMENTS

~----- 4.4 x 1019 NVT (avg) l CHARPY IMPACT COMPARTMENTS

\\

\\

\\

J

~----"---- 4.6 x 1019 NVT (avg)

).

FIGURE 6.. CAPSULE A-240 DIAGRAM WITH FLUENCE (E>l MeV) RESULTS

r-,

! 1 ::*

l !... J r-:*

i ;

u f j

[1

.J n

I L__

( ':

l L....-

)

\\

20 t

TO CORE u

Ti Fe s

Ued Nied Cued T 1.62 1.9 1

2 3

i,.

5 6

7

' " l

.4 5 6

.452 i-c...-------3.81 ---'"------~ *"*

FLUX SPECTRUM HOUSING

- -~

! TO CORE I

/

I

+

4

.542

- +

3 2

I l

.411 i

-+

I

~~~-

I

.411

-+

I I

I i

.542.

I I

I I

~

E~~~

I 2.3~5905-----+1 3.81---------..i FLUX ATIENUATION HOUSING 304 STAINLESS STEEL*

• ~

1.9 I

I l FIGURE 7.

DIAGRAM OF FLUX SPECTRUM AND FLUX ATTENUATION HOUSINGS (All Dimensions in Centimeters)

( __

1*-

J

/..

I J

\\

[ __.*

r *-.

(.

r--

1 :

L_*

r --~

I

(.

)

\\.. ~'

1-c I

I ;*

I I '*-

t.-

i I

(

I I

L I

L.

i. -**

~*

---

~

21 TABLE 6.

FAST NEUTRON DOSIMETRY RESULTS (E>l MeV) FOR PALISADES Location in Capsule TOP Attenuation Set Fluence Set Fe (avg)***

MID Attenuation Set Fe 4.31 x 1019 4.31 x 1019 4.27 x 1019

4. ~9 x 10 19

-t~

3.88 x 1019**

4.14 x 1019 4.26 x 1019 4.38 x 1019 4.49 x 1019 4.34 x 1019 4.73 x 1019*

3.95 x 1019**

Fluence Set 4.34 x 1019 Fe (avg)*** = 4.39 x 1019 BOTTOM Attenuation Set Fluence Set Fe (avg),'<**

4.61 x 1019 4.76 x 1019 4.52 x 1019 5.02 x 1019*

4.20 x 1019**

4.51 x 1019 4.60 x 1019 2

Fast Fluence (n/cm )

Ni Cu 3.93 x 1019 3.98 x 1019 4.32 x 1019 19

.4.38 x 10 5.10 x 1019

• These wires were positioned forward 0.411 cm (toward core) of the first three in this set.

• • These wires were positioned behind 0.411 cm (away from core) the first three in this set.

Ti 5.23 x 1019

• • • Average of three center attenuation monitors and one center fluence monitor.

I_:

1-1 -

L.

I I

I i '.

\\*

L_

L.J

) -,

i -

\\,.__.**

(_ ___.

(-.

I I

22 The_lead_fac_tQr.,._i_d~.* _,_t_he_~_a.t;i,Q_Q_f_t]J._E; _ _(-l_ue!J..G_E; __.;i._l;___t:_Q.§ __ ~_.;:i,p_sJJle_f;_Q the_largesJ:_f_luenc e_.r:e.c.ei.veci _b,y__the __,wall. at... any ___ az imu_thal..,v;ra.J.l_lQ_ca tion, was __ calc.ula te c! __ to_J~e _19_,j._.. bas e9, _ o_-q_ _:QQ_'t__I_~s~1t..~_._J1i,_1}..§_!:_h_~J-1~--~ g_e.E.L.V uell.f§,

a:t:_t:h.e.._y_e_s_s_el_w.all_at.__the_time_ of~caps.ule...A-:::2-4.0 __ r__emqval __ (2.*. 2_6~eqµi_valent fol 1 power years, EFPY) is 2. 28 *x 1 018 n/c.nC.___The_p_r.e.dic.t..e.d __ peak_wall f lu_~nc!;_(.E~M_eY)_af.t.er_3_2-..EEE.Y.__is.._then_3_._23__x_lQ.~c;m~_._Th_i,_s~Qmp p._~es weU_w.i.J::_h__J;_b_g__t_e_ch-ni~a.Lsp.e,c_if_ka.t:i,.o_n ( 19 ) y_gJ.µ~J-~ _ _,__QLx 1 Q~

9.

A_t_t_he._az_imuthaLlo.cat j on of ma xi m1 im wa 1 1 f J ue.nce_(.c.ir.c_u:m£er_en.ti.al mesh 5) the fl,__ue_l1._C_~_at_ll_LT_is_W_8_x_l~/cm 2 or 0_.__5_6_that._ar._t_he_irner

~~lJ,2y.rJ~c e,_aJ~_c_o rding~_to_the_DOT~c.alc. ulations

• As shown in Figure 7, wires 4 and 5 of the attentuation sets were offset from the capsule center and the fluence measurements for these wires confirm this fact.

The average rate of drop of fluence in the top compartment can be calculated from the measured values to be 20.4%/cm, in the middle compartment 21.9%/cm, and in the bottom compartment 21.6%/cm.

These compare well with a calculated value (by the DOT 3.5 Code) of 26.37%/cm at the center of the capsule cross section.

The full power flux and the actual flue;ce at the location of capsule A-240 in the Palisades reactor were calculated from dosimeter acti-vation analyses using the DOT 3.5 computer program.

The DOT 3.5 computer program(2l) calculated the neutron energy spectrum at the capsule for 22 neutron energy groups.

The P3s8 approximation was used in the calculation.

The "spectrum averaged" activation cross sections for iron, nickel, copper, and titanium were also calculated by the code.

The DECAY computer program was then used to combine the cross sections of the monitors, the measured gamma activity, and the actual reactor power history into the desired result which is the flux and fluence at the monitor position.

The integrated neutron fluence at a surveillance location is determined from the radioactivity induced in irradiated detector materials.

A known amount of an element to be activated is placed in the neutron flux.

Atoms of the dosimeter material interact with the neutron flux producing a radioactive product; After exposure the gamma radiation from the dosimeter is measured and used to calculate the flux required to produce this level of activity.

The fluence is then calculated from the integrated power output of the reactor during the exposure interval.

[_ __.

r--.

l r*

I I

1***

(_ __

\\ ~

~*

I i

c. -

L __

I -

i 23 The activity A induced into an element irradiated for a time ti in a constant neutron fltL~ is given by where cr(E) = the differential cross section for the activation reaction

¢(E) = the neutron differential flux N = the atom density of the target nuclei (atoms/g)

-1 A= the decay constant of the product atom (sec

).

If the sample is permitted to decay for a time t between exposure and w

counting, then the activity when counted is A "spectrum-averaged cross section" may be defined as

!: cr (EH (E) dE cr =

<Xl

! ¢ (E)dE 0

and the integrated flux as

<Xl

¢ = ! 0 ¢ (E)dE Then

/'° cr (EH (E) dE =

0

/"' cr (E)¢ (E)dE 0

<Xl

¢ (E)dE 0

<Xl

¢ (E)dE = cr¢ 0

so that the activity A may be written as The flux is then computed from the measured activity as A

i

i. --

i t..

r* -,

I I_.

! c -

r**-~

I L_

r'" :.

)

I

\\__

\\

L

' I

(

' I

\\ --

24 If it is desired to find the flux of neutrons with energies: above a given energy level, E, the cross section corresponding to this energy level is c

defined as where Then cr(E>E )

c q,(E>E )

c 00 cr (E)cjl(E)dE 0

= f E q,(E)dE c

CD cr (E)cjldE =

0 0 cr (E)cjl (E) dE f E q, (E)dE c

= cr (E>E ) q, (E>E )

c c

!; q, (E)dE c

a,nd the activity A may be written as

-At*

-At A= Ncr(E>E

)~(E>E )(1-e l)e

w.

c c

In case that the neutron flux is not constant the dosimeter activity at the time of removal from the reactor is where A

c Ncr(E>E )q,(E>E )C c

c J

l:

j=l

f. (1-e -ATj) e -A (T-t j)

J J

number of time intervals of constant flux

f. J T. J

t.

J T

the fractional power level during the time interval j the time length of interval j the elapsed time from beginning of irradiation to end of interval j the time from beginning of irradiation to counting.

L...

r**~,

\\

I \\..

r:

I I_~

i

\\..

' L..

,--L.

r..

I l.,

i.

r l l

L.

Then A

<P(E>E ) = ----

c Ncr(E>E )C c

25 This is the equation used to find fluxes based on surveillance dosimeter activations.

The time intervals are taken as one month each and average power during the month is used for values of f.

The DOT 3.5 calculation was performed to find the spectrum averaged activation cross sections for the flux monitors.

DOT is a computer program which solves the Boltzmann transport equation in two-dimensional ge~metry.

The method of discrete ordinates is used.

Balance equations are solved for the density of particles moving along discrete directions in each cell of a two-dimensional spatial mesh.

Anisotropic scattering is treated using a Legendre expansion of arbitrary order.

The two-dimensional geometry that was used to model the Palisades reactor is shown in Figure 8.

As seen there are 20 circumferential divisions and 48 radial divisions.

Capsule A-240 includes circumferential,meshes 8, 9, and 10 and radial meshes 26, 27, and 28.

Third order scattering was used (P3) and 48 angular directions of neutron travel (24 positive and 24 negative) [S8 ]

were used.

Neutron energies were divided into 22 groups ranging from 14.9 MeV energy down to 0.01 MeV energy.

The 22 group neutron structure is that of the RSIC Data Library DLC/Cask(22), and neutron absorption, scattering, and fission cross sections used are those supplied by this library.

The core shroud and the core support barrel are stainless steel type 304.

The reactor vessel is A302B steel.

The reactor core was mocked up as homogenized fuel and water having the same densities as found in the operating reactor.

The fuel was a source of neutrons having a u235 fission energy spectrum.

The neutron spectrum at the center of the capsule as calculated by DOT is shown in Figure 9.

Also shown for comparison is the fission spectrum.

Both spectra have been normalized to contain one neutron above 1.0 MeV.

It is seen that the DOT spectrum and the fission spectrum do not differ appreciably.

However, the DOT calculated values of "spectrum averaged" cross section crR differ from the fission-spectrum-averaged cross sections by as much as 20 percent.

.* L, L.J

( '

j

\\....

l....

r~

L_;

I

(_

~..

1--

L __

f

[_ '

f ~

l..

L..

I

(__

I.

l '.

i j

\\ *...;

~

C')

al 240.03f---t--.... -~

I 218.441--r--;..../ _...L 146.331 U'J a:

UJ 1-UJ

2 i= z UJ u 2

Cl

~

a:

I I

I I I I

I I

I I

26 CORE SHROUD FIGURE 8.

PALISADES GEOMETRY USED IN DOT RUN PRESSURE VESSEL CAPSULE A240 CORE SUPPORT BARREL

~-*

I

\\ ___.

)

l...

( ~

I L..

)

( -

l,

i.. __ __

I I c -

~

a: -

~.

z

~

i a:

u w

c..

Cl)

(!)

a:

w 2 w 27

- --*I -

---

1

+-- -**-- ---

1

[

I L-:=.. -=-----*--;------- -

- --- I i

l I +

I I

I FISSION SPECTRUM 1 SPECTRUM AT CAPSULE

___ __J I

• -1

~---~----..__ _______ _

10*2 1---- -

1------- --- -- t---- --

!------+------+-- - --- -------

--. - -----i------'

---

* *--.- -----~

---

~

I I i 10 *3 4-------l------- -- -** ----- ------- ---t-* ----*

1------+-- -------*-- --- ------ - -- ---

1----.,--1---- -- ----

10*1=.---+------------~---~----~-~~ ~-=-:-____ --=-_: __________ - - - -

1-----+-------------------------- ---* -- --- ____________ _.

!------+----~------------------- ----------

!------+-- ------* --*---.. - ---,----

---

____ ___l. _____ ___,

I i

i II 10-s1---------+--------i--,------+--l------~---------------+-!-------t, 0

2 4

6 8

10 12 14 NEUTRON ENERGY /MeV FIGURE 9.

COMPARISON OF THE NEUTRON FISSION SPECTRUM WITH THE DOT CALCULATED SPECTRUM AT THE CAPSULE

l _:

r*

l...

• L.

r*

L i

l...

r**

i

\\ -

28 Based upon the fluxes calculated by DOT at the nine capsule meshes used in the DOT calculation to represent the capsule, effective cross sections cr(E>l.O MeV) =

f~ cr (E) ¢ (E)dE 0

f~

¢ (E)dE 1.0 were calculated for iron, nickel, copper, and titanium in each of the capsule meshes.

These results are shown in Table 7.

Using the results of Table 7 and flux monitor geometry shown in Figure 7, plots of cross section versus position can be used to interpolate cross sections for each of the positions in the flux spectrum sets and in the flux attenuation sets.

These values and other nuclear constants are given in Table 8.

These constants together.with the power history(l9) and the sample activity were used in the DECAY computer program to calculate the flux and fluence at the capsule.

Thermal Monitors The capsule contained four types of low melting point alloy thermal monitors which were in the form of a helix.

This was located below a stainless stee_l weight inside a quartz tube.

Four thermal monitors, one each of each type as indicated in Table 2 were placed in each of the three tensile, thermal monitor, anc;l dosimeter compartments.

The thermal monitors were each examined at a magnification of about 4X using a stereomicroscope for evidence of melting.

In addition, photographs were taken of each group of four thermal monitors from a given compartment at a magnification of about 4X.

These are shown in Figures lOA, lOB, and lOC.

Based on the thermal monitor examinations, it appears that the capsule was not above 536 F in the region of any of the three sets of thermal monitors for any period long enough to cause melting.

r*-

' I -~

I

r.

I I

(

L_~*

I I

I I

i -

i l...

29 TABLE 7.

CROSS SECTIONS FOR THE WIRE MONITORS (E>l.O MeV) IN NINE MESHES

~Core 6.972 x 10-4 7.001 x 10-4 7.300 x 10-4 7.059 x 10-4 7.019 x 10-4 7.399 x 10-4 7.359 x 10-4 7.309 x 10-4 7.070 x 10-4 Copper Cross Sections (Barns)

~Core

.1214

.1213

.1243

.1217

.1207

.1246

.1246

.1232

.1267 Nickel Cross Sections (Barns)

+Core I

.0902

.0901

.0927 I

---

*-*-* -r---.--~**.. **- ***-

.. 0905 I

.0897

.0930

.0930

.0919

.0948 Iron Cross Sections (Barns)

+Core

.0132

.0132

.0136

.0132

.0131

.0137

• -..................,...._.,.._,_-:':'t':"'==I..=.=:..-=~.,-- ---* ------*** ******----------

.0137

.0135

.0141 Titanium Cross Sections (Barns)

(.-*

30 TABLE 8.

CONSTANTS USED IN DOSIMETRY CALCULATIONS r--

Isotopic Threshold Cross Section

Target, Abundance,

Energy, Product (Barns)

Reaction (MeV)

Half-Life Position E>l.O MeV Fe54(1,p)Mn54 99.865 Fe 5.82 1.5 314 d F3*

.0897 Al*"'(

.0918 A2

.0897 A3

.0902 L -

A4

.0902 AS

.0908

l.

63 60 99.999 Cu 69.17 5.0 5.26 yr F7

.00075 Cu (n,a)Co

.58 58 Ni (n,p)Co 99.951 Ni

67. 77 LO 71.3 d F6

.1228 T.46(

)S 46 i

n, p c

99.793 Ti 7.93 2.5 83.8 d F2

.0132

• F refers to fluence set, 3 to position.

• • A refers to attenuation set, 1 to position.

I -

I l -

I 1

• I I \\

536F 558F 580F 590F FIGURE lOA.

THERMAL MONITORS FROM TOP TENSILE COMPARTMENT NO. 1614

I r.

I I

I I -

I I

536F 558F 580F FIGURE lOB.

THERMAL MONITORS FROM MIDDLE TENSILE COMPARTMENT NO. 1641 590F

i.

l.

I

[_.

I l

l -

i l_

536F 558F 580F FIGURE lOC.

THERMAL MONITORS FROM BOTTOM TENSILE COMPARTMENT NO. 1673 590F

\\

l l~

r-1 I

1-I I L.

I.

34 Charpy Impact Properties 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 9 through 12. In addition to the impact energy values, the tables also list the measured values of lateral expansion and the estimated fracture appearance for 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 directly adjacent to the notch location.

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

The impact data are graphically shown in Figures 11 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.

Figures 15 through 18 show the fracture surfaces of the Charpy specimens.

Table 13 summarizes the Palisades 30 and 50 ft-lb transition tempera-ture, the 35 mils lateral expansion*temperature, and the upper shelf energy for the present program and for the earlier unirradiated program.

As indicated previously in the neutron dosimetry section, the Charpy specimens received a fairly uniform exposure.

The neutron exposures based on the iron dosimeters ranged from 4.3 to 4.6 x 1019 n/cm2 (>1 MeV).

Particular exposure values can be assigned to each of the four Charpy materials since specimens of a particu-lar material were all located in a given Charpy compartment.

Using a conserva-tive approach, the four Charpy materials from Capsule A-240 received exposures estimated as follows:

Base longitudinal, 4.5 x 1019 n/cm 2 (>l MeV)

Base transverse, 4.4 x 1019 n/ cm 2 (>l MeV)

Weld, 4.6 x 1019 n/cm 2 (>l MeV)

HAZ, 4.3 x 1019 n/cm 2 (>l MeV)

The impact properties of the Palisades base metal, weld metal, and HAZ metal are all significantly affected by irradiation, as can be seen in the figures of impact energy and lateral expansion versus temperature (Figures 11 through 14).

35 l

TABLE 9.

CHARPY V-NOTCH IMPACT RESULTS FOR PALISADES r

BASE METAL, LONGITUDINAL ORIENTATION l.

Test Impact Lateral Fracture

Temp, Energy, Expansion, Appearance, t '

Specimen F

ft-lb mils

% Shear 126 80 4.0 2.8 2

L:

124 125 8.1 13.2 30 r ~:

121 150 15.7 16.8 17 I

[_;

12A 175 18.8 20.6 21 r**

125 200 28.5 30.2 32

l.

UP 225 38.5 30.0 44 r*

122 250 55.0

51. 6 55 l..

123 275 58.5 57.4 61 r*

12B 300 82. 0 72.6 100 12C 400 86. 0 78.6 100 c

llT 400 106.0 86.6 100 127 450 95.0 82.2 100 l

~

I*

I TABLE 10.

CHARPY V-NOTCH IMPACT RESULTS FOR PALISADES I, _

BASE METAL, TRANSVERSE ORIENTATION Test Impact Lateral Fracture

Temp, Energy, Expansion, Appearance, Specimen F

ft-lb mils

% Shear l

235 80 5.0 4.6 5

232 125 11.5 14.4 14 231 150 15.0 17.4 17 22T 175 18.0 22.0 27 233 200 25.0 28.0 29 237 225

31. 5 34.4 39 22U 250 39.0 32.8 42 234 275 52.5 52.4 55 236 275 53.9 52.8 58 22Y 300 68.0 66.6 100 23A 350 69.0 67.0 100 22P 400 67. 9 65.4 100

I

(

36

1.

TABLE 11.

CHARPY V-NOTCH IMPACT RESULTS FOR PALISADES I

WELD METAL r*

I Test Impact Lateral Fracture

Temp, Energy, Expansion, Appearance, Specimen F

ft-lb mils

% Shear 31C 80 4.2 4.0 3

335 125 5.8 5.0 3

32E 150 4.2 2.0 5

I I..

332 175 9.0 7.6 10

(

I 31J 200 21.8 26.2 38 I (.

331 250 15.5 14.0 25 r

32U 275 15.0 18.8 38 l

327 300 48.3 49. 4 95 f ~

31K 325 54.5 50.6 98 32T 400 43.0 37.2

-90 l

31L 400 55.5 59.6 100 32P 450 45.0 43.6 100 TABLE 12.

CHARPY V-NOTCH IMPACT RESULTS FOR PALISADES HAZ METAL

( -

Test Impact Lateral Fracture

Temp, Energy, Expansion, Appearance, Specimen F

ft-lb mils

% Shear 44U 80

11. 7 11.0 16 46T 125 15.0 16.6 23 45T 150 31.4

31. 2 37 43T 175 28.0 28.4 25 44T 200 27.0 32.8 41 43U 200 32.0 34.6 44 46U 225 28.0 30.2 37 45U 250 56.0 59.2 99 42U 300 62.0 62.6 99 42T 350 56.0 56.4 100 41U 400 65.0 65.2 100 41T 400 56.5 55.6 100

I I.

I.,

I I '*

I I

L 1-1 L*

f.

~-*

l '.

l

\\

I f

I l

I.

OD 37 Unirradiated Baseline Irradiated Capsule A-240 140 120

..c 100 I.... -

Cl C1l 80 c:

LU -

u.,, a.

E 60 40 20 o--*

/'.

I *

.I 0

~*

/

I

• I

• I ***

0 -+-~"'-~~~..,.-~~--~~..,.-~~-.-~~~

. ~~--l 100 80 60 40 20 0

-200

- 100 0

100 200 300 400 500 Temperature, F FIGURE 11.

CHARPY IMPACT PROPERTIES FOR BASE METAL, PLATE NO. D3803-l, LONGITUDINAL ORIENTATION

~

.E c:

0 *v; c:

<'O a.

x LU

<'O C1l -

<'O

....J

i 38 I. :*

(

100 r--

0 0 Unirradiated Baseline r l.

Irradiated Capsule A-240 0

80 l

~

{.

.E c

I 60 0

• v; Ii c

I._

ro.

a.

.J x

r -

L.U i

40 ca L-'

(1)

,f.

ro

_J L.

20 r-*

I I

I 0

140 r -

I I L -

I -

120

.D 100 I --

I Cl 0.)

80 l -

c L.U u

ro a.

E 60 0

I 40 20 0

-200

-100 0

100 200 300 400 500 Temperature, F FIGURE 12.

CHAR.PY IMPACT PROPERTIES FOR BASE METAL,

PLATE NO. 03803-1, TRANSVERSE ORIENTATION

L.'

I l.

l L.

r,

I

(.

r.

I i

• I l.

r.

t.

I I.

..0 C'l Q.l c UJ u

~

Q.

r-c:

100 80 60 40 20 39

• ~

. /~..

/..

0+-~~...,....~~-r~~---~~--r-~~---r~~~.~~---4

-200

-100 0

100 200 300 400 500 Temperature, F FIGURE 13.

CHARPY IMPACT PROPERTIES FOR WELD METAL

I_.

r I.

~*

I OD I l.

\\

I

(_.

r-I 1.. -*

[

r-( __

I I __ -

r-I -

L_

r.. L.

L r.

r I I

(__

r l L

~ -

40 Unirradiated Baseline Irradiated Capsule A-240 I

D

/

140 0

120 0

0

..c 100 I --

Cl 80 c

UJ -

u co Q.

0 E

60 40 I

20

/

0 I

-200

-100 0

100 200 300 400 Temperature, F FIGURE 14.

CHARPY IMPACT PROPERTIES FOR HEAT AFFECTED ZONE METAL 100 80

.::2.E c

60 0

c co a.

x UJ 40 co

~

co

_J 20 0

500

~*

r I t

(.

I L r,

L r*-

I i

I r

I l_

r -

• ~*

I

(.

I I

l.

I..

Specimen Identification 126 124 121 12A 125 llP

+80

+125

+150

+175

+200

+225 Test Temperature, F Specimen Identification 122 123 12B 12C llT 127

+250

+275

+300

+400

+400

+450 Test Temperature, F FIGURE 15.

CHARPY IMPACT FRACTURE SURFACES FOR PALISADES CAPSULE A-240, BASE METAL LONGITUDINAL ORIENTATION

l.

\\

l J I L.

r -

L

,~

I

~.

l -

Specimen Identification 235 232 231 22T 233 237 80 125 150 175 200 225 Test Temperature, F Specimen Identification 22U 234 236 22Y 23A 22P 250 275 275 300 350 400 Test Temperature, F FIGURE 16.

CHARPY IMPACT FRACTURE SURFACES FOR PALISADES CAPSULE A-240, BASE METAL TRANSVERSE ORIENTATION

r

\\

r I

[_

t

[ __

I L.

r.*

l I

r I_

L.

Specimen Identification 31C 335 32E 332 31J 80 125 150 175 200 Test Temperature, F Specimen Identification 32U 327 31K 32T 311 275 300 325 400 400 Test Temperature, F FIGURE 17.

CHARPY IMPACT FRACTURE SURFACES FOR PALISADES CAPSULE A-240, WELD METAL 331 250 32P 450

r I l.

l.. -

Specimen Identification 44U 46T 45T 43T 44T 80 125 150 175 200 Test Temperature, F

• Specimen Identification 46U 45U 42U 42T 41U 225 250 300 350 400 Test Temperature, F FIGURE 18.

CHARPY IMPACT FRACTURE SURFACES FOR PALISADES CAPSULE A-240, RAZ METAL 43U 200 41T 400

r I **

I r

l -

' I I_.

( -

l 45 TABLE 13.

SUMMARY

OF CHARPY IMPACT PROPERTIES FOR PALISADES Flue nee E>l MeV, 30 ft-lb 19 2 Transition Material Program x 10 n/cm Temp, F Base L(a)

Ref 10 0

0 Base L (a)

Present 4.5

+205 Base T (b)

Ref 10 0

25 Base T(b)

Present 4.4

+230 Weld Ref 10 0

- 85 Weld Present 4.6

+265 HAZ Ref 10 0

-90 HAZ Present 4.3

+200 (a)

Base metal, longitudinal orientation.

(b)

Base metal, transverse orientation.

Upper so ft-lb Shelf Transition Energy, Temp, F ft-lb

+20 165

+250 95

+55 105

+270 68

-50 120

+305 54

-65 125

+240 60 35-Mil Lateral Expansion Temp, F

+5

+220

+40

+235

- 85

+285

-55

+205 For the four materials in Capsule A~240, the 50 ft - lb and 30 ft-lb transition temperatures range from 240 F to 305 F and 200 F to 265 F, respectively.

The 35-mil lateral expansion temperature ranges from 205 F to 285 F, and the upper shelf energy levels range from 54 to 95 ft-lb.

The upper shelf energy levels were taken as being the highest point of the curve drawn through the points.

r

• 46 Table 14 i s a comparison of the 50 ft-lb and 30 ft-lb trans ition temperature shifts and t he 35-mil lateral expansion temperature shift due t o irradiation for the present pr ogram.

The 50 ft-lb transition temperature shift is defined as the increase in the irradiated 50 ft-lb temperature with respect to the unirradiated 50 ft-lb temperature.

The 30 ft-lb transition temperature shift and the 35-mil lateral expansion temperature shift are similarly defined.

As can be seen, the greatest shift occurs for the weld material in all three cases.

TABLE 14.

50 FT-LB, 30 FT-LB, AND 35-MIL LATERAL EXPANSION TEMPERATURE SHIFTS DUE TO IRRADIATION FOR PALISADES CAPSULE A-240 30 ft-lb 50 ft-lb 35-Mil Lateral

Fluence, E>l MeV, Transition Transition Expansion 19 2

Temperature Temperature Temperature Material x 10 n/cm

Sqift, Base L(a) 4.5 Base T(b) 4.4 Weld 4.6 RAZ 4.3 (a)

Base longitudinal orientation.

(b)

Base transverse orientation.

+205

+205

+350

+290 F

Shift, F

Shift, 230 215 215 195 355 370 305 260 In comparing the 50 ft-lb shift to the 35-mil lateral expansion shift for each of the four materials, note that the weld metal 35-mil lateral expansion shift is greater than the weld metal 50 ft-lb shift, but the reverse is true for the other three materials.

F In considering the Charpy results, it should be realized that this surveillance capsule is an accelerated one, and has a very high lead factor of 19.4.

This means the flux the specimens in the capsule receive is much higher than any point in the vessel wall.

Further Palisades capsules to be examined include ones with significantly lower lead factors, more closely approximately the vessel wall.

The actual location of the various surveillance capsules inside the pressure vessel are given in Figure C-1 of Appendix C.

I.

l.

I I.

\\ -

47 The reference temperature, RTNDT' was determined previously for the unirradiated base transverse material to be 0 F(23).

The procedure for the determination of the RTNDT is defined by the ASME Boiler and Pressure Vessel Code( 24 )

Appendix H, "Reactor Vessel Material Surveillance Program Requirements", to 10CFRSO specifies how an adjusted reference temperature for irradiated specimens can be determined. (2S)

This temperature can be used in revising the plant pressure-temperature operating curves in those cases where the fluence of the irradiated specimens is in the range to be experi-enced by the pressure vessel.

The adjusted reference temperature defined by Appendix H is determined by adding to the reference temperature the amount of the temperature shift in the Charpy curves between the unirradiated material and the irradiated material, measured at the SO ft-lb level, or that measured at the 35-mil lateral expansion level, whichever temperature shift is greater.

Tensile Properties The tensile properties determined for the tensile specimen contained in the Palisades capsule A-240 are listed in Table 15.

The table lists test temperature, fluence, 0.2 percent offset yield strength, ultimate tensile strength, uniform elongation, total elongation, and reduction in area for the present program as well as for the unirradiated baseline program.

Post-test photographs of the tensile specimens are shown in Figure 19.

These photographs show the necked down region of the gage length and the fracture.

A typical tensile test curve is shown in Figure 20; the particular test shown is for base metal specimen 1D4 tested at 72 F.

Tensile tests were run at room temperature (69 to 73 F), 535 and 565 F.

The higher temperature tests exhibited a decrease in 0.2 percent offset yield strength and a decrease in ultimate tensile strength for each material with respect to the room temperature tests.

In general, ductility values (as determined by total elongation and reduction in area) decreased at higher temperatures as compared to room temperature for each material.

Palisades tensile specimens were located in the vicinity of iron d

h" h d fl from 4.3 to 4.6 x 1019 n/cm2 osimeters w ic receive uences ranging (E>l MeV).

When the tensile data for Capsule A-240 is compared to the unirradiated baseline data (Table S) it can be seen that as fluence increases, the yield strength and tensile strength increase while ductility decreases.

48 I

TABLE 15.

TENSILE TEST RESULTS FOR PALISADES CAPSULE A-240 I

0.2 %

Offset Ultimate

Fluence,

[_

19 2

Test Yield Tensile Reduction Elongation Spec 10 n/cm

Temp, Strength,

Strength, in Area,

Uniform, Total, Material No.

(E>l MeV)

F psi psi i

Base L 0

70 63790 85540 72.10 15.8 30.9 1-Base L 1D4 4.4 72 92783 110407 61.56 10.5 20.9 I

Base L 0

535 57410 82460 64.6 12.0 23.2 Base L lDl 4.4 535 81422 102388 41.70 8.2 14.0 Base L 0

565 58350 84590 66.30 13.6 25.2 Base L 1D5 4.4 565 81305 102701 45.74 9.1 16.2 Weld 0

70 64270 81910 70.06 17.4 32.3 L -

Weld 3DA 4.6 73 115331 124857 46.45 9.0 16.5 Weld 0

535 63680 84600 55.73 12.7 21.6 1*

Weld 3DB 4.6 535 95722 109979 45.55 7.0 14.3 Weld 0

565 60500 83980 55.96 13.5 23.1 Weld 3D7 4.6 565 93789 109760 39.90 7.9 14.3 HAZ 0

70 6'3660 84440 69.00 15.5 29.6 r-HAZ 4D4 4.3 69 96352 113963 59.55 7.8 17.4 I_

HAZ 0

535 58309 81910 64.37 12.5 22.4 HAZ 4D7 4.3 535 83287 103906 50.74 7.0 15.2 HAZ 0

565 55710 82370 65.07 14.2 25.3 HAZ 4D5 4.3 565 83435 104803 55.32 7.2 15.6

• The 0 fluence values represent the average of the three unirradiated baseline specimen results for the given material and test temperature.

r*

\\ -

r J

I FIGURE 19.

POSTTEST PHOTOGRAPHS OF PALISADES TENSILE SPECIMENS FROM CAPSULE A-240 Material:

Base Longitudinal Specimen:

1D4 Test Temperature:

72 F Material:

Base Longitudinal Specimen:

lDl Test Temperature:

535 F Material:

Base Longitudinal Specimen:

1D5 Test Temperature:

565 F Material:

Weld Specimen:

3DA Test Temperature:

73 F Material:

Weld Specimen:

3DB Test Temperature:

535 F

! l.

r -

l -

( L.

r FIGURE 19.

(Continued)

Material :

Weld Specimen:

3D7 Test Temperature:

565 F Material:

RAZ Specimen:

4D4 Test Temperature:

69 F Material:

RAZ Specimen:

4D7 <

Test Temperature:

535 F Material:

RAZ Specimen:

4D5 Test Temperature:

565 F

i i

I c-*

L_,

r-I L_~

I L'

r---,

L:

i I

17

'1 t-.~

r**-*

i '

L:

c r:

' ~-*

1 r-l

~-*

I I

• ~--

r-I L r

I l l...

L.

l _. '..

• c;;

110 100 90 80 70 51 u;*so

(/) e en 50 40 30 20 10 o._~~~~--"'~~~~~--~~~~~.i.....---~~--..... ~~~~~....i 0

5 10 15 20 Percent Elongation FIGURE 20.

TYPICAL STRESS STRAIN CURVE Curve shown is for base metal specimen No. 1D4 tested at 72 F.

25

I I

. r.

I :

I l **

l.J'

\\j 1 c.. ~

• ~* -~

\\..

f'

\\.

L~

i

~-

I l,

(

l -

i.

• 52 CONCLUSIONS A postirradiation examination program was conducted at the Battelle Columbus Hot Laboratory on the Palisades Capsule A-240.

The capsule was irradiated for 2.26 effective full power years at the 240 degree location on the outside of the core support barrel of the reactor vessel.

Based on the iron monitors, the average fluences (E>l MeV) for the capsule and the vessel 19 2

18 2

wall inner surface were 4.4 x 10 n/cm and 2.3 x 10 n/cm, respectively.

The capsule did not appear to be above 536 F in the region of any of the three sets of thermal monitors.

The tensile properties are in the normal ranges for highly irradiated material with the yield strength and ultimate strength increasing and the ductility generally decreasing.

Charpy impact tests were run to generate Charpy curves and determine the changes in the 30 ft-lb transition temperature, the 50 ft-lb transition temperature, the 35 mil lateral expansion, and the upper shelf energy levels for the base longitudinal, base transverse, weld, and HAZ materials.

The highest 50 ft-lb transition temperature (305 F), the highest 30 ft-lb transition temperature (265 F), and the greatest 35-mil lateral expansion temperature (285 F) occur for the weld metal.

The upper shelf energy varies from 54 ft-lb to 95 ft-lb for the four materials, with the weld metal having the lowest upper shelf energy level.

I.

t 1**

I-.

(_;

' --" L I,

L.

l ' '--*

r..

53 REFERENCES

1.

Reuther, T. C., and Swilsky, K. M., "The Effects of Neutron Irradiation on the Toughness and Ductility of Steels", in Proceedings of Toward Improved Ductility and Toughness Symposium, published by Iron and Steel Institute of Japan (October, 1971), pp 289-319.

2.

Steele, L. E., "Major Factors Affecting Neutron Irradiation Embrittlement of Pressure-Vessel Steels and Weldments", 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,~. 1 (1963).

4.

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).

5.

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 Materials Special Technical Publication 481 (1969) pp 47-102.

6.

Integrity of Reactor Vessels for Light-Water Power Reactors, Report by the USAEC Advisory Committee on Reactor Safeguards (January, 1974).

7.

Groeschel, R. C., Summary Report on Manufacture of Test Specimens.and Assembly of Capsules for Irradiation Surveillance of Palisades Reactor Vessel Materials, CE Report No. P-NLM-019, (April 1, 1971).

8.

"Surveillance Tests on Structural Materials in Nuclear Reactors", ASTM Designation El85-73, Book of ASTM Standards, Part 45 (1974), pp 621-627.

Perrin, J. S., "Nuclear Reactor Pressure Vessel Surveillance Capsule Examinations:

Application of American Society for Testing and Materials Standards", paper presented at the October, 1977, International Atomic Energy International Symposium on Application of Reliability Technology to Nuclear Power Plants (Reliability Problems of Reactor Pressure Components) in Vienna, Austria, and to be published in the Proceedings of the Conference.

Perrin, J. S., Farmelo, D. R., Jung, R. G., and Fromm, E. 0., "Palisades Pressure Vessel Irradiation Capsule Program:

Unirradiated Mechanical Properties", (August 25, 1977).

11.

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

12.

"Determining Neutron Flux, Fluence, and Spectra by Radioactivation Techniques", ASTM Designation E261-77, Annual Book of ASTM Standards, Part 45.

j

\\

t_:

f '

L:

L'.

• 1

).

I

\\_"'

54 tYi

13.

"Determining Fast-Neutron Flux by Radioactivation of Iron", ASTM Designation E263-77, Annual Book of ASTM Standards, Part 45.

14.

"Determining Fast-Neutron Flux by Radioactivation of Nickel", ASTM Designation E264-77, Annual Book of ASTM Standards, Part 45.

15.

"Measuring Fast-Neutron Flux Density by Radioactivation of Copper, ASTM Designation E523-76, Annual Book of ASTM Standards, Part 45.

16.

"Measuring Fast-Neutron Flux by Radioactivation of Titanium",

ASTM Designation E526-76, Annual Book of ASTM Standards, Part 45.

17.

Perrin, J. S., Fromm, E. 0., and Lowry, L. M., "Remote Disassembly and Examination of Nuclear Pressure Vessel Surveillance Capsules", Proceedings of the 25th Conference on Remote Systems Technology, American Nuclear Society (1977).

18.

"Mechanical Testing of Steel Products", ASTM Designation A370-75, Book of ASTM Standards, Part 10 (1976), pp 28-79.

19.

Private Communication, Jenkins, R. B., to Perrin, J. S., February 28, 1978.

20.

Drawing 2966-E-2871, by Jenkins, R. B., at the request by phone conversation of Jung, R. G., February 7, 1979. *

21.

RSIC Computer Code Collection, DOT 3.5 -

Two Dimensional Discrete Ordinates Radiation Transport Code, Radiation Shielding Information Center, Oak Ridge, National Laboratory, Oak Ridge,Tennessee.

.22.

RSIC Data Library Collection, CASK-40, Group Coupled Neutron and Gamma-Ray Cross Section Data, Radiation Shielding Information Center, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

23.

Addendum to Reference (10).

Letter from Perrin, J. S., to Jenkins, R. B.,

November 22, 1977, regarding RTNDT of Base Transverse Material for Palisades.

24.

"Rules for Construction of Nuclear Power Plant Components", ASME Boiler and Pressure Vessel Code,Section III, American Society of Mechanical Engineers, (1974 Edition).

25.

"Licensing of Production and Utilization Facilities", Title 10, Code of Federal Regulations, Part 50, Appendix H, U.S. Government.

! t *.

I i.*

r*~

L..

r

\\.... 1'

/.

c l......

)

l I

I '-.-

I APPENDIX A INSTRUMENTED CHARPY EXAMINATION

I I

~~-

I L L

[

[

..... ~ I_.

i

~

1

• j

\\.

APPENDIX A INSTRUMENTED CHARPY EXAMINATION INTRODUCTION The radiation-induced embrittlement of the pressure vessel of a commercial nuclear reactor is monitored by evaluation of Charpy V-notch impact specimens in surveillance capsules.

In a conventional Charpy V-notch impact test, the information obtained for each specimen includes the absorbed energy, the lateral expansion, and the fracture appearance.

Curves of energy versus temperature and lateral expansion versus temperature can be drawn for a series of specimens of a given irradiated material tested over a range of temperature.

These curves, when compared to similar curves for the unirradiated material, show the shift in behavior due to irradiation.

The curves can be used to determine the adjusted reference temperature, RTNDT' by establishing the shifts in temperature between unirradiated and irradiated curves corresponding to the 50 ft-lb energy level and the 35 mils lateral expansion level.

Additional information can be determined from a Charpy V-notch impact test by using instrumented equipment to perform an instrumented Charpy V-notch impact test.

This test provides load-time information in addition to the energy absorbed.

The loads during impact are obtained by instrumenting the Charpy striker or tup with strain gages, so that the striker is essentially a load cell.

The details of this technique have been.reported previously. (l, 2)

The additional information obtained from the instrumented Charpy test is the general yield load, PGY (plastic yielding across the entire cross section of the Charpy specimen), the maximum load, P

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

The area under the load-time curve corresponds to the total energy absorbed, which is the only data obtained in a normal uninstrumented Charpy test.

The instrumented test, however, allows separation of the energy absorbed into (1) the energy required to initiate ductile or brittle fracture (premaximum load energy), (2) the energy required for ductile tearing (postmaximum load energy), and (3) the energy associated with shear lip formation (postbrittle fracture energy), as shown in Figure A-1.

r-,

1.

L:

' u r-, u 1;

t;c' r-~

i'*

[

r~

[

[

I I te "C

ca 0

-I General Yield Load, PGY A-2

\\

Maximum Load, P max

\\

~

a,;ttlo F"""" Load, PF Pre "Maximum-Load" Energy 1----Timo to a.;n1......... -----"*-.-4' TI me

~

Post."Maximum-Load" Energy

~

Post Brittle-Fracture Energy

~IGURE A-1.

AN IDEALIZED LOAD-TIME HISTORY FOR A CHARPY IMPACT TEST

I i t 1-,

I

\\. : re L

C' L.

-r-*--..

1 i l.__)

r-'.

\\ /)

\\: u c~

• ~..

r-:

[j r:

LC r~ ;*

1.. __

• r *:

(.:"

I i -*

r_

i I

L~

r \\. L A-3 In a normal Charpy impact study, the energy absorbed is determined as a function of temperature to obtain the Charpy impact curve and the 30/50 ft-lb transition temperatures.

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(3-6) have developed theories that permit a detailed analysis of the load-temperature diagram.

This diagram can be divided into four regions of fracture behavior, as shown in Figure A-2.

In each region, different fracture parameters are involved. (l)

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

• EXPERIMENtAL PROCEDURES The general procedures for the instrumented Cha~py test are the same as those for the conventional impact test, and are described in the main text of this report.

The additional data are obtained through a fairly simple electronic configuration, as shown in the schematic diagram of Figure A-3.

The striker of the impact machine is modified to make it a dynamic load sensor.

The modification consists of a four-arm resistance strain gage bridge positioned on the striker to detect the compression loading of the striker during the impact loading of the specimen.

The compressive elastic strain signal resulting from the striker contacting the specimen is conditioned by a high-gain dynamic amplifier and the output is fed into a digital oscilloscope.

The load-time information is digitized and displayed on the screen of the digital oscilloscope.

It is subsequently plotted on an x-y recorder.

The load-time history as a function of test temperature forms the basis for further data analysis.

The digital oscilloscope is triggered by a solid-state device at the correct time to capture the amplifier output signal.

1-*

I '--1.

L 1:'

L :

I I ~

L

(-*-~

i I l :

Cll.....

fl>

A-4

, I

'T Region 1 Region 2 Region 3 Test Temperature

'pmax PF Region 4 FIGURE A-2.

GRAPHICAL ANALYSIS OF CHARPY IMPACT DATA

i -.

I I,

\\._, *'

,-~

i *,

I...

• re L.

)'

L_;

f"':

L :

r-*

L.. '

1

• j.

L.

\\

l...

i I

(

• Bridge Balance and Amplifier Shunt Resistance A-5

~

Hammer

/

I Ir

)

\\ -

IJ

./

Oscilloscope Triggering Device FIGURE A-3.

DIAGRAM OF INSTRUMENTATION ASSOCIATED WITH INSTRUMENTED CHARPY EXAMINATION

i :

I \\..

c-l

' L :.

I.

I

\\. -

r" L i-.

L.

I,_.

r I

\\

I I

\\~-

A-6 RESULTS AND DISCUSSION Specimens of four materials were tested.

These materials are base metal longitudinal orientation, base metal transverse orientation, weld metal, and heat-affected-zone (HAZ) metal.

The instrumented Charpy results are presented in Table A-1.

The table lists the specimen number, test temperature, impact energy, general yield load, and maximum load.

The load time curves are presented in Figures A-4 through A-7.

It can readily be observed that the features of the load-time curves change as a function of temperature.

The energy values listed in the Table are those obtained from the impact machine dial.

Each curve falls into one of the six distinctive notch-bar bending classifications shown in Figure A-8.

The pertinent data used in the analysis of each record are the general yield load (PGY) and the maximum load (P

).

max The Charpy energy-temperature curves and the load-temperature curves obtained are shown in Figures A-9 through A-13.

In general, the curves show both the general yield load and the maximum load initially increasing as the temperature is de~reased from the upper shelf region of the Charpy impact curve.

As the temperature is further decreased through the transition temperature region, the general yield load continues to increase.

However, as the temperature is decreased through the transition temperature region and into the lower shelf region, the maximum load is seen in a number of the curves to go through a maximum and to then drop off sharply.

( -

I A-7 r-,

TABLE A-1.

CHARPY IMPACT DATA FOR PALISADES CAPSULE A-240 I

• re General l__'.

Impact Yield Maximum 1-,

Specimen

Temp, Energy, Point

Load, L_

Material Identification F

ft-lb PGY' lb PMAX, lb Base L 126 80 4.0 2975 I

L~

Base L 124 125 8.1 3300 Base L 121 150 15.7 3250 3800

[*-

Base L 12A 175 18.5 3175 3900 L '.

Base L 125 200 28.5 3150 4075 Base L UP 225 38.5 3050.

3925 r-;

Base L 122 250 55.0 3025 4250

{ '

Base L 123 275 58.5 Base L 12B 300 82.0 2900 4000 (i

Base L 12C 400 86.0 2775 3825 I

I *.

\\ ___

Base L llT 400 106.0 2825 4050 Base L 127 450 95.0 2825 4000 f--I'.

Base T 235 80 5.0 L~

Base T 232 125 11.5 3400 3875 c:

Base T 231 150 15.0 3200 3800 L

Base T 22T 175 18.0 32.00 3650 Base T 233 200 25.0 3150 3925 f"'

Base T 237 225 31.5 3100 3925 I

Base T 22U 250 39.0 3100 3950

~*

Base T 234 275 52.5 3100 4125 Base T 236 275 53.9 3100 4000 Base T 22Y 300 68.0 2825 3950 I.

Base T 23A 350 69.0 2800 4100 l~>

Base T 22P 400 67.9 2825 3925 Weld 31C 80 4.2 3375 Weld 335 125 5.8 3775 r-Weld 32E 150 4.2 3150 j '

Weld 332 175 9.0 3600 4025

'\\_.....

Weld 31J 200 21.8 3250 3850 r**

Weld 331 250 15.5 3475 4200 Weld 32U 275 15.0 3450 3925 Weld 327 300 48.3 3125 3900

\\

Weld 31K 325 54.5 3125 4050 Weld 31L 400 55.5 2850 3775 Weld 32T 400 43.0 3375 4050 Weld 32P 450 45.0 3225 4025 I l.

HAZ 44U 80

11. 7 I-.

HAZ 46T 125 15.0 3300 4000 i

HAZ 45T 150 31.4 3325 4175 L..

HAZ 43T 175 28.0 3275 4200 i

HAZ 43U 200 32.0 3275 4050

(

HAZ 44T.

200 27.0 3050 3825 HAZ 46U 225 28.0 3125 4025 re HAZ 45U 250 56.0 3150 3950 HAZ 42U 300 62.0 3025 3850 HAZ 42T 350 56.0 3225 4000 HAZ 41T 400 56.5 2975 3725 HAZ 41U 400 65.0 2950 4025

__ _J

i '

t-~*

r-"'

i -i-*

) '

1~*

L:

r*

I L _

r--

i_~

1-:

I

\\

r-*

\\__:

i"""'!.

I l_:

r:

(_ __

,-'"'. Le 1-*-

I 1 *

! -t I i r

I L I-*

I

' (

e A-8 SPECIMEN NO.:

126 4,000-TEST TEMPERATURE (F):

80 3,000

~

IMPACT ENERGY DIAL (FT-LB):

4.0

-c'

"' 2,000 0

..J GENERAL YIELD LOAD. PGY (LB):

1000 MAXIMUM LOAD, PMAX (LB):

2975 0

0 200 1!00 600 Time, µ.sec 4,000 SPECIMEN"NO.:

124 125 3,000 TEST TEMPERATURE (F}:

~

8.1

"'C 2,000 IMPACT ENERGY DIAL (FT-LB):

0

..J GENERAL YIELD LOAD, PGY (LB):

1,000 3300 MAXIMUM LOAD, PMAX (LB):

0 0

100 200 300 Time, µ.sec 8,000 SPECIMEN NO.:

121 TEsi: TEMPERATURE (F):

150 6,000 IMPACT ENERGY DIAL (FT-LB):

15.7

~ 4,000

"'C 0

3250

..J GENERAL YIELD LOAD, PGY (LB):

2,000 MAxlMUM LOAD, PMAX (LB):

3800 0

0 200 400 600 Time, µ.sec FIGURE A-4.

INSTRUMENTED CHARPY IMPACT DATA FOR PALISADES CAPSULE A-240 BASE METAL LONGITUDINAL ORIENTATION

'(_.

r-*

A-8a J

\\. i.

8,000 SPECIMEN NO.:

12A I

I *.....

175 6,000 TEST TEMPERATURE (F):

(__,

==

IMPACT ENERGY DIAL (FT-LB):

18.5

-c" 4,000 Q

L

..J GENERAL YIELD LOAD, PGY (LB):

3175 2,000

\\

/_ ':

MAXIMUM LOAD, PMAX (LB):

3900 0

r~

{i 0

200 400 600 Time, µsec r--

! \\ __ ;

8,000 L;

SPECIMEN 'NO.:

125 r;

200 6,000 TEST TEMPERATURE (F):

L~

==

28.5

-c* 4,000

[.

IMPACT ENER.GY DIAL (FT-LB):

Q

..J.

GENERAL YIELD LOAD, PGY (LB):

3150 2,000

(-

I.

~.-

4075 MAXIMUM LOAD, PMAX (LB):

0 L

0 800 1,200 Time, µsec 1

• I 8,000 r

SPECIMEN NO.:

llP

\\.

225 6,000 I -

TEST TEMPERATURE (F):

(

IMPACT ENERGY DIAL (FT-LB):

38.5

== 4,000 r -

-c*

Q 3050

..J GENERAL YIELD LOAD, PGY (LB):

2,000

(-'

I L MAXIMUM LOAD, PMAX (LB):

3925 0

I I

0 400 800 1,200 I.

Time, µsec 1**

~ -

FIGURE A-4.

(Continued) 1

~ -*

\\ f u n

I I.

I

(

r*,

l j *.

L.

(

I **

A-Sc SPECIMEN NO.:

llT TEST TEMPERATURE (F): __

4~0~0 __

IMPACT ENERGY DIAL (FT-LB): -~10~6~.

0~-

GENERAL YIELD LOAD, PGY (LB): --'2"""'8'""2""'5'----

MAXIMUM LOAD, PMAX (LB): __

4"'"'0"""5'"""0 __

SPECIMEN NO.:

127 TEST TEMPERATURE (F): _4_5_o __ _

IMPACT ENERGY DIAL (FT-LB):

95'. 0 GENERAL YIELD LOAD, PGY (LB):

2825 MAXIMUM LOAD, PMAX (LB):

4000 8,000 6,000

"'O. 4,000 0

...J 2,000 0

0 800 1,600 2,400 Time, µsec 8,ooo~--------------.

6,000

! 4,000

"'O 0

...J 2,000 0

I 0 800

• 1,600 2,400 Time, µsec FIGURE A-4.

(Continued)

I..

I l -

f -

(

A-9 1**

8,000 SPECIMEN NO.:

232

l__,

6,000 TEST TEMPERATURE (F):

125 I"

L IMPACT ENERGY DIAL (FT-LB):

11.5

=

4,000 f_.

-c*.,

Q GENERAL YIELD LOAD, PGy (LS):

3400

...I 2,000 r~

MAXIMUM LOAD, PMAX (LB):

3875

(:

0

(-.

0 400 600 L

Time, µ.sec r~

8,000 SPECIMEN NO.:

231

[

150 6,000 TEST TEMPERATURE (F):

[

=

IMPACT ENERGY DIAL (FT-LB):

15.0

-o* 4,000 Q

[.

...I GENERAL YIELD LOAD, PGy (LB):

3200 2,000 1-MAXIMUM LOAD, PMAX (LB):. ** 3800 I.

l..*

0 i:.

c 200 400 600 Time, µsec c*

L.

8,000 r

SPECIMEN 'NO.:

22T 6,000 TEST TEMPERATURE (F):

175

=

l..

IMPACT ENERGY DIAL (FT-LB):

18.0

"'c.

4;000 Q

l _

...I GENERAL YIELD LOAD, PGy (LB):

3200 2,000 1_

• MAXIMUM LOAD, PMAX (LB):

3650 0

I 1*

r 200

.QO 600 Time, µsec FIGURE A-5.

INSTRUMENTED CHARPY IMPACT DATA FOR PALISADES CAPSULE A-240 BASE METAL TRANSVERSE ORIENTATION

r-*,

I A-9a 8,000 SPECIMEN NO.:

233 L

6,000 TEST TEMPERATURE (F):

200

[*

25.0

5! 4,000 IMPACT ENERGY DIAL (FT-LB):

-o*

r:

ra Q

L_;

GENERAL YIELD LOAC, PGY (LB):

3150

...I 2,000

\\'

MAXIMUM LOAD, PMAX (LB):

3925 L;

0 c:

0 400 800 1,200 l.\\

Time, µsec l :

8,000 SPECIMEN NO.:

237 l_:

225 6,000 TEST TEMPERATURE (F):

r*

5!

t; IMPACT ENERGY DIAL (FT-LB):

31.5

-o*

ra*

Q r:

...I L.*

GENERAL YIELD LOAD. PGY (LB):

3100 2.000

(-'.

MAXIMUM LOAD, PMAX (LB):

3925 l.:

0 r:

0 400 800 1,200 l._

Time, µsec L:

8,000 r-SPECIMEN'NO.:

22U 6,000 TEST TEMPERATURE (F):

250 r

5!

[ _,

IMPACT ENERGY DIAL (FT-LB):

39.0

-o* 4,000 Q

...I

... l GENERAL YIELD LOAD, PGY (LB): 3100 2,000 r**-

3950 L

MAXIMUM LOAC, PMAX (LB):

0 I

0 400 800 1,200 Time, µsec i.e FIGURE A-5.

(Continued)

r ~

A-9b l*:

8,000

r.

SPECIMEN NO.:

234 l

6,000 TEST TEMPERATURE (F): 275 I,

L IMPACT ENERGY DIAL (FT-LB):

52.5

E 4,000

-o*

r~

ca 0

u 3100

-I GENERAL YIELD LOAD, PGY (LB):

2.000 f *:

MAXIMUM LOAD, PMAX (LS):

4125 t.. :

0

, r:

0 400 800 1,200 l }

Time, µ.sec r-:

I \\_'

8,000 SPECIMEN NO.:

236 ti L_i 275 6,000 TEST TEMPERATURE (F):

r-;-

E

\\ (__;

IMPACT ENERGY DIAL (FT-LB):

53.9

-c*

ca 0

[;

-I GENERAL YIELD LOAD, PGY (LB):

3100 2,000 r-* '

MAXIMUM LOAD, PMAX (LB):

4000 L:

0 f.1 0

400 800 1,200 I ;

Time, µsec L_;

,--~

I r 8,000 SPECIMEN 'NO.:

22Y I

6,000 300 TEST TEMPERATURE (F):

r L_

"O 4,000 IMPACT ENERGY DIAL (FT-LS):

68.0 ca 0

-I r

L GENERAL YIELD LOAD, PGY (LS):

2825 2,000

( -

L..

MAXIMUM LOAD, PMAX (LB):

3950 0

0 400 800 1,200 Time, µsec

e FIGURE A-5.

(Continued)

f *.

r.

I '

r:

I :

f ~*

L.:

i ; t ]

r~

1 ;

l._;

n I

l_;

L r

l

{

I i.*

A-9c 8,000 SPECIMEN NO.:

23A 6,000 TEST TEMPERATURE (F):

350 IMPACT ENERGY DIAL (FT-LB):

69.0

9 4,000

-o*

ca 0

GENERAL YIELD LOAD, Pay (LB):

2800

~ 2,000 MAXIMUM LOAD, PMAX (LB):

4100 0

8,000 SPECIMEN NO.:

22P TEST TEMPERATURE (F):

400 6,000

9 IMPACT ENERGY DIAL (FT-LB):

67.9

-o* 4,000 0

~

. GENERAL YIELD LOAD, Pay (LB):

2825 2,000 MAXIMUM LOAD, PMAX (LB):

3925 0

FIGURE A-5.

(Continued) 0 800 1,600 2,400 Time, µsec 0

800 1,600 2,400 Time,,usec

r t re 1

LI.

c-,

i I.

L_.

(,;

A-10 SPECIMEN NO.:

31C TEST TEMPERATURE (F):..__;.s_o __ _

IMPACT ENERGY DIAL (FT-LB): _4_._2 __ _

GENERAL YIELD LOAD, Pay (LB): -----

MAXIMUM LOAD, PMAX (LB):

3375 SPECIMEN NO.: --'3;..;3;;...;5'----

TEST TEMPERATURE (F): --=l;.;::2..:;.5 __ _

IMPACT ENERGY DIAL (FT-LB): _5_._8 __ _

GENERAL YIELD LOAD, PGY (LB):-----

MAXIMUM LOAD, PMAX (LB): _3_7_7_5 __

4000 3000

.Q

-.2000 -

Q

-I 1000 6,000

-c* 4,000 Q

-I 2,000 0

0

Zoo 400 600 Time, µsec 200 400 600 Time, µsec s,000-.---------------.

SPECIMEN 'NO,:

32E TEST TEMPERATURE (F): _1_50 __ _

IMPACT ENERGY DIAL (FT-LB): _4_._2 __ _

GENERAL YIELD LOAD, Pay (LB):-----

MAXIMUM LOAD, PMAX (LB): _3_1_5_0 __

6,000-1l 4,ooo-o

-I 2.ooo~A o-I 0

I I

I

• 1 200 4uO Time, µ.sec FIGURE A-6'.

INSTRUMENTED CHARPY IMPACT DATA FOR PALISADES CAPSULE A-240 WELD METAL GOC

r A-lOa

[ f.

8,000 SPECIMEN NO.:

332 L

6,000 r--

TEST TEMPERATURE (Fl: 175 L.

IMPACT ENERGY DIAL (FT-LSI: 9.0

S 4,000 r*-:

-o*

i_ __

Q 3600

-I GENERAL YIELD LOAD, PGY (LSI:

2,000

[

MAXIMUM LOAD, PMAX (LSI: 4025 0

r

• ~

L' 0

200 400 600 Time, µ.sec r--

I L. _:

8,000 31J I~

SPECIMEN NO.:

i

"-~-

6,000 TEST TEMPERATURE (Fl:

200 i

r

S L

IMPACT ENERGY DIAL (FT-LB):

21.8

-o* 4,000 r*-*

Q

-I GENERAL YIELD LOAD, PGY (LB):

3250 2,000 MAXIMUM LOAD, PMAX (LSI:

3850 L _,

0 r*-

0 400 800 1,:!00 l_'

Time, µ.sec L.:

8,000

• • -I SPECIMEN 'NO.:

331 t

250 6,000 f

TEST TEMPERATURE (F):

S 15.5

-0 4,000 IMPACT ENERGY DIAL (FT-LB):

Q i

-I l

3475 GENERAL YIELD LOAD, PGY (LB):

2,000 r

I l_

MAXIMUM LOAD, PMAX (LB): 4200 0

400 800 1,200 Time, µsec r**

FIGURE A-6.

(Continued)

A-lOb

[.

8,000 SPECIMEN NO.:

32U I

275 6,000 1-*

TEST TEMPERATURE (F):

I I

IMPACT ENERGY DIAL (FT-LB): 15.0

S 4,000

~*

L._J ca Q

..J GENERAL YIELD LOAD, PGY (LB): 3450 2,000 MAXIMUM LOAD, PMAX (LB):

3925 0

I 0

400 800 1,200 Time, µsec I

8,000 SPECIMEN NO.:

327 TEST TEMPERATURE (F):

300 6,000 IMPACT ENERGY DIAL (FT-LB):

48.3 "t:l 4,000 ca Q

...I GENERAL YIELD LOAD, PGY (LB):

3125 2,000 MAXIMUM LOAD, PMAX (LB):

3900 0

{ -

0 800 1.600 2,400 Time, µsec 8,000 SPECIMEN "NO.:

31K 325 6,000 i

TEST TEMPERATURE (F):

S 54.5

~ 4,000 IMPACT ENERGY DIAL (FT-LB):

ca Q

..J GENERAL YIELD LOAD, PGY (LB):

3125 2,000 MAXIMUM LOAD, PMAX (LB):

4050 0

I 0

800 1,600 2,400 Time, µsec FIGURE A-6.

(Continued)

I l ~

A-lOc

\\ -

8,000 SPECIMEN NO.:

311 6,000 TEST TEMPERATURE (F):

400

\\.

IMPACT ENERGY DIAL (FT-LBJ:

55.5

9 4,000 1*-

-o*

ca

\\..

Q 2850 GENERAL YIELD LOAD, PGY (LS):

2,000 I i.

MAXIMUM LOAD, PMAX (LBJ:

3775 L_:

0

[

D 800 1,600 2,400 Time, µ.sec r~

I L.

8,000 SPECIMEN NO.:

32T r-~

[ __

400 '

6,000 TEST TEMPERATURE (F):

r:

I.

9

\\."

IMPACT ENERGY DIAL (FT-LBJ:

43.0

'"O 4,000 r~

Q _,

I __

GENERAL YIELD LOAD, PGY (LS):

3375 2,000

[

MAXIMUM LOAD, PMAX (LB):

4050 0

[

0 800 1,600 2,400 Time, µsec r*-

I I

L._

8,000 SPECIMEN "NO.:

32P

\\.

6,000 TEST TEMPERATURE (F):

450 I --

e I

l...

45.0

'"O -4.ooo IMPACT ENERGY DIAL (FT-LBJ:

Q _,

\\.. -

GENERAL YIELD LOAD, PGY (LB):

3225 2,000 r *-

l.

MAXIMUM LOAD, PMAX (LB):

4025 0

I 0

I I

800 1,600 2,400 I

Time, µsec FIGURE A-6.

(Continued)

\\._..

I l

I l...:

L_..

L....'

l...

r*-

i

\\.

A-11 SPECIMEN NO.:

46T TEST TEMPERATURE (F): _1_2_5 __ _

IMPACT ENERGY DIAL (FT-LB):

15

• 0 GENERAL YIELD LOAD, PGY (LB): _3_3_o_o __

MAXIMUM LOAD, PMAX (LS):

4000 6,000

S 4,000

~* =

0

...I 2,00Q 0

0 200 400 600 Time, µsec 8,000-r-------------

SPECIMEN NO.:

45T TEST TEMPERATURE (F): __

1_50 __ _

IMPACT ENERGY DIAL (FT-LS): __

3_1_._4 __

GENERAL YIELD LOAD, Pav (LS): __

3_3_2_5 __

MAXIMUM LOAD, PMAX (LB): __

4_1_7_5 __

SPECIMEN 'NO.:

43T TEST TEMPERATURE (F):

175 IMPACT ENERGY DIAL (FT-LS): __ 2.._8_.;...0;...__

GENERAL YIELD LOAD, PGY (LS): __

3_2_7_5 __

MAXIMUM LOAD. PMAX (LB): __

4_2_o_o __

6,000

S

~* 4,000

=

0

...I 2,000 0

6,000

-s*

Q 4,000

...I 2,000 0

0 400 800 Time, µ.sec 0

400 800 Time, µsec FIGURE A-7.

INSTRUMENTED CHARPY IMPACT DATA FOR PALISADES CAPSULE A-240 HEAT AFFECTED ZONE METAL 1,200 1,200

\\

i :*

i..

f *-*

r l

I I

I

\\.

I,

L~

f I

I.:

r.

I.

l....

L.

\\.

I_,

r**

i I l \\ l.

r.*

A-llc SPECIMEN NO.:

41T TEST TEMPERATURE (F): ___;:4'"""0""'0'----

IMPACT ENERGY DIAL (FT-LB):

56.5 GENERAL YIELD LOAD, PGY (LB):

2975 MAXIMUM LOAD, PMAX (LB):

3725 SPECIMEN NO.:

41U TEST TEMPERATURE (F): __

4_0_0 __

IMPACT ENERGY DIAL (FT-LB): __

6_5_._0 __

GENERAL YIELD LOAD, PGY (LB): __

2_9_50 __

MAXIMUM LOAD, PMAX (LB): __

4_0_2_5 __

FIGURE A-7.

(Continued) 6,000

=

4,000

-o*

Q

...J 2,000 0

0 800 1,600 2,400 Time, µsec s,0001-.---------------

6,000

=

-o" 4,000 Q

...J 2,000 0

0 800 1,600 2,400 Time, µ.sec

I l

r*

(

r**.

L:

r-L_,

I c L n r-:

L_.

f* ~...

I I L

(

/._ __

r-,

!~*

I

\\

i

{_~

\\

\\ '

I I t _

I-.

f i..... -

c*

)_.

Fracture Type II 111 IV v

VI "C

0

-I "C

0

-I "C

0

-I "C

0

-I "C

0

-I "C

0

-I A-12 Load-Displacement Raw Curves Data PF Deflection PGY Deflection PGY Deflection PGY*

pmax Deflection p*GY*

pmax Deflection Deflection Remarks Brittle fracture Brittle fracture Brittle fracture followed by fracture indicative of shear lip formation Stable crack propagation followed by unstable brittle fracture and fracture indicative of shear lip formation Stable crack propagation followed by fracture indicative of shear lip formation Stable crack propagation followed by gross deformation FIGURE A-8.

THE SIX TYPES OF FRACTURE FOR NOTCHED BAR BENDING

' i

i.

\\.

I. r*

\\. -~

I~ '-*

\\

I~

\\;

i :

\\..-~*

I..

I

\\..

I -

t.,

I I

4500 4000

-g 3500 0

....J 3000 2500-Legend 0

PMAX

6. PGY D E A-13 0

D 100 D

75 50 25 0

100 200 300 400 500 Temperature, F FIGURE A-9.

INSTRUMENTED CHARPY LOAD-TEMPERATURE Ai'ID ENERGY-TEMPERATURE CURVES FOR PALISADES m

i re c..o I

CAPSULE A-240, BASE-METAL LQNGITUDINAL ORIENTATION

l I,

I

. i*

r *-

I.

LJ r~

I I l 1...... !

( *,,

.I '

I '

~-

\\

i i l.c

~ -*.

(

I L_,.

I, I

L _

i I_ j.

4000

~ 3000 0

A-14 Legend 0 PMAX

.6 PGY D E 75 50 25

..._,....._,....._,....._--,....._,....._,....._~,....._,....._,.....__,..,....._,....._,....._,....._,....._,....._,....._,....._-o 0

100 200 300 400 500 Temperature, F FIGURE A-10.

INSTRUMENTED CHARPY LOAD-TEMPERATURE AND ENERGY-TEMPERATURE CURVES FOR PALISADES CAPSULE A-240, BASE METAL TRANSVERSE ORIENTATION m

l co

~

tC er

1..

c**.

I L

r*

I

[

f

~

1*

. r*

~ l :

'. j""

1*--

l..,

I 1 *.. -*

I :

\\ '

4000

~ 3000 0

_J A-16 0

0 0

Legend 75 50 25 i--,__,__,__,.__,__,____,,__,__,__,__,__,__,__~,__~~---l.0 0

100 200 300 400 500 Temperature, F FIGURE A-12.

INSTRUMENTED CHARPY LOAD-TEMPERATURE AND ENERGY-TEMPERATURE CURVES FOR PALISADES CAPSULE A-240, HAZ METAL m

<1)...,

tC I

a-

r--

) \\.

I

\\. -~

r--

l__

1--

i

(_ __

I i ( __ -

1-*-

A-17 CONCLUSIONS The instrumented Charpy impact test technique was used to obtain load-time inf orniation as a function of temperature for the Palisades pressure vessel materials.

The general yield load was shown to increase as the temperature is decreased, with the maximum load going through a maximum for a number of the materials.

r*

(_

{--**~

(~--

' i.

L __

1'.

I.

~**

I

.._ __ ~*

('*

I i

L -*

t. _.

A-18 APPENDIX A REFERENCES A-1.

Wullaert, R. A., "Applications of the Instrumented Charpy Impact Test",

in Impact Testing of Metals, American Society for Testing and Materials Special Technical Publication 466, p 148 (1970).

A-2.

Perrin, J. S. and Sheckherd, J. W., "Current and Advanced Pressure Vessel Surveillance Specimen Evaluation Techniques", Proceed~ngs of 21st Conference on Remote Systems Technology, American Nuclear Society (1973).

A-3.

Wilshaw, T. R. and Pratt, P. 0., "The Effect of Temperature and Strain Rate on the Deformation and Fracture of Mild-Steel Charpy Specimens",

in Proceedings of the First International Conference on Fracture, Sendai, Japan, September, 1965, l* p 973.

A-4.

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

A-5.

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

A-6.

Fearnehough, G.D. and Hoy, C. J., "Mechanism of Deformation and Fracture in the Charpy Test as Revealed by Dynamic Recording of Impact Loads",

Iron Steel Inst., 202, 912 (1964).

r

\\...*

L _;

f-

~~

• L.

c:

I

~-

APPENDIX B COMPOSITIONAL ANALYSIS OF SURVEILLANCE TEST MATERIALS

L.

I' L..:

~

I L:

r---

\\

I

( __,

r.

1 I '----

r: c:.:

r i

L_

i '---

l _

t_ __

r..

[ -~*

i.*

APPENDIX B COMPOSITIONAL ANALYSIS OF SURVEILLANCE TEST MATERIALS The sample chamical analyses of the surveillance test materials for the three plates and two welds that make up the surveillance program as reported by Combustion Engineering, Inc. (a) are given in Table B-1.

The base metal test material was fabricated from Plate No. 03803-1.

The weld metal test material was fabricated by welding together intermediate shell Plate Nos. 03803-1 and 03803-2.

The heat-affected-zone test material was fabricated by welding together intermediate sh'el1 Plate Nos. 03803-2 and 03803-3.

(a)

See Reference (7) in main text.

r i '

I I :

l__,

i L

[

I B-2 TABLE B-1.

SAMPLE CHEMICAL ANALYSIS OF SURVEILLANCE TEST MATER.IALS D3803-3/

D3803-l (a)

D3803-2 D3803-3 D3803-2(b)

Elements Plate Plate Plate Weld Root Si

.23

.32

.24

.24 s

.019

.021

.020

.009 p

.Oll

.012

.010

.011 Mn l.SS 1.43 l.S6 1.08 c

.22

.23

.21

.098 Cr

.13

.42

.13

.OS Ni

.S3

.SS

.S3

.43 Mo

.S8

.S8

-.S9

.S4 Al

.037

.022

.037 Nil v

.003

.003

.003 Nil Cu

. 2S

. 2S

.25

.2S (a)

Used to fabricate base metal specimens.

(b)

Used to fabricate RAZ.metal specimens.

(c)

Used to fabricate weld metal specimens.

@ 2 in.

Face

.2S

.010

.012 1.03

.*080

.04 1.28

.S3 Nil Nil

.20 D3803-2/

D3803-l (c)

Weld @ 2 in.

Root Face

.2S

.22

.010

.010

.Oll

.011 1.01 1.02

.088

.086

.OS

.03

.63

1. 27

.SS

.S2 Nil Nil Nil Nil

.26

.22

t -.

(--

r--

1

( __

r-l..

I.

(_,

r-:

(__:

I" I,

[ __

~--*

APPENDIX C IN-REACTOR LOCATION OF SURVEILLANCE CAPSULE ASSEMBLIES

' l __

I l__

I L_

r-

~

L.

I, _ _:

( --

t l._~

' i

[.

i_

APPENDIX C IN-REACTOR LOCATION OF SURVEILLANCE CAPSULE ASSEMBLIES The location of the various surveillance capsule assemblies within the Palisades pressure vessel are shown schematically in Figure C-1.

The present capsule A-240 was irradiated in the 240 degree azimuthal location

[

[

[

L_

1-*

I l___

f -

l [_.

C-2 Accelerated -----------..

---

Wall A-60 W-80 Reactor Vessel ----.

.---------Wall W-100 Core Shroud Wall------

W-290 Wall ---------~~n~~~

....... -..Jll"""'~~~£_------ Wall W-280 W-260 Core-----

Support Barrel Reactor---~

Vessel Wall Capsule Assembly FIGURE C-1.

Plan View

---

Accelerated Capsule Assembly

---

Thermal Elevation View LOCATION OF THE PALISADES SURVEILLANCE CAPSULE ASSEMBLIES Capsule Assembly