ML20107E074
| ML20107E074 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 11/05/1984 |
| From: | Landow M, Lowry L, Perrin J Battelle Memorial Institute, COLUMBUS LABORATORIES |
| To: | |
| Shared Package | |
| ML112991343 | List: |
| References | |
| BCL-585-84-2, BCL-585-84-2-R01, BCL-585-84-2-R1, NUDOCS 8502250332 | |
| Download: ML20107E074 (123) | |
Text
.. _ , _ ____._ _____ _ ~ _ _ _ _ _ . . _ _ _ _.. ___2_._...___..;_._..._._.
D II *
'l BCL-585-84-2 Revision 1 1
1 FINAL REPORT on i
EXAMINATION, TESTING, AND EVALUATION OF IRRADIATED PRESSURE VESSEL SURVEILLANCE SPECIMENS FROM THE MONTICELLO NUCLEAR GENERATING PLANT to
/
'T
. NORTHERN STATES POWER COMPANY November 5, 1984
! by L L. M. Lowry, M. P. Landow, J. S. Perrin, l A. M. Walters, R. G. Jung, and R. S. Denning l
i BATTELLE Columbus Laboratories
. 505 King Avenue 3 8502250332 850215 Columbus, Ohio 43201 PDR ADOCK 05000263 P PM Battelle is not engaged in research for advertising, sales promotion, or publicity purposes, and this report may not
- l. be reproduced in full or in part for such purposes.
! marre ct s - c o cu m m u m
'l
- - . , . - . --- - - - - . ~ ~.
-- ~
_ . _ _ . . .. .~ _ . .__
.+
LIST OF CHANGES FOR BCL-585-84-2 REVISION 1 Page Line Changes Cover Upper Right Added Revision 1 to "BCL-585-84-2" Cover 9 Date changed from March 15, 1984 to November 5, 1984 vi 8 Page number changed from A-23 to A-24 vi 11 Page number changed from A-24 to A-2T vi 14 Page number changed from A-25 to A-2K vi 17 Page number changed from A-26 to A-27 1 15 Date changed from March 15, 1984 to November 5, 1984 2 3 Inserted e into indicated (typo) 2 4 Inserted reference numbers (16 37 15 6 Corrected 25, 25, and 22 to N, N) and 24 15 12 Corrected "five" to six and "Your7 ,to three
' _16 Top Column 4, line 2 JD4 corrected to JDA (typo) 16 Top Column 5, line 5 Corrected by removing (a) 16 Top Column 6, lines 5&8 Corrected by removing (b) 16 Lower Column 2, line 1 DE3 corrected to DE2 (typo) 16 Lower Column 4, top line Corrected b) to (
16 Lower Column 6, line 1 Corrected b) to (
16 Lower Column 6, line 2 Corrected a) to ( )
16 Lower Column 7, line 2 Corrected a) to ( )
42 2 Corrected " fifteen to thirteen and " eleven" 1
to thirteen 42 5 Corrected 300 F to 225 F i
42 7 Corrected 225 F to 706 F' 44 Table 8, line 6 Removed JKA, -30, 7T 7, 54.0, and 50 44 Table 8, line 15 Removed JKS, 300, 113.0, 82.0, and 100 45 Table 9, between lines 3&4 Inserted JKA, -30, 71.3, 54.0, and 500 45 Table'9, between lines 10 & 11 Inserted JKS, 300, 113.0, 82.0 and 100 49 Figure 15 Removed points at -70TT71 TT a,nd 30UT-
_(113.0) 50 -Figure 16 Removed points at -30F (54.0) and 300F (82.0) 51 Figure 17 Removed points at -30F (50) and 300F (100) 52 Figure 18 Inserted points at -30F (71.3) and 300F (113.0)
. 53 Figure 19 Inserted points at -30F (54.0) and 300F (82.0) 54 Figure 20 Inserted points at -30F (50) and 300F (100) 56 . Figure 22 Removed photo of JKA from top row and-JKE from bottom row 57 Figure 23 Inserted photo of JKA in top row and JK_5_
5 (typo) in bottom row ,
58 Table 10 Values for Weld corrected, -65 to -50
-25 to _15, -40 to -37 and 122 to 1~d a
marre ct s - cocu m nu s 3 _ .- - ... -
- 7. . _ __
~
i ~ Z _ - - _ __ __ -.---s -- - -- - -
3 x i
Page Line Changes 58 Table 10 Values for HAZ corrected,.-57 to -67, -15 to 36 to -45 and 121 to 118 59 1 C Fr,ected 122'Tt-lb to 129 f Ulb and 121 ft-lb to 118 ft-lb 62 15 Removed "(and in some cases totally)" and inserted for base and HAZ metal specimens, and the ultimate and fracture strengths appear to recover totally 62 19 Removed "all three" and inserted base and HAZ material types and between 75F and 200 F for the weld material type ~
62 21 Removed "6 to 13" and added (about 6 percent) 62 22 After 500 F. added the sentence, Weld
?
specimen tension tests were conducted at 75 and 200 F.
63 Table 11 JCl, JC2, and JBM were corrected from weld to Base and JB2 and JB6 were corrected from Base to Weld. One inch gauge length values (in parenthesis) were deleted for JB2 and JB6 and added for JC1, JC2, and JBM. The table was arranged to give Base RT, 200, and two.550 F 4
results first, the Weld RT and 200F results next, and the HAZ RT, 200, and 500F results last.
l 63 Table 11 Footnote (1), "if" corrected to is (typo) 64 Figure 24 Plot corrected to reflect TABLE II ~
corrections
' 65 Figure 25 Plot corrected to reflect TABLE 11 corrections -
66 Figure 26 Photos corrected to reflect tensile specimen corrections 67' Figure 27 Photos corrected to reflect tensile specimen corrections I 77 5
' Corrected 122 ft-lb to 129 ft-lb and 121 ft-lb to 118 ft-lb 77 15 For clarity, aHod " copper" (0.17 weight %)
"and phosphorus" (0.01 wei<ht %)
A-8 Table A-2, line 6 Removed JKA, -30, 71.3, 34E 2, 4668, 4227, and 1847 A-8 Table A-2, line 14 Corrected JEV to JEU (typo)
A-8 Table A-2, line 15 Renoved JK5, 300,1I3.0, 2529, 3636, N/A, and N/A A-9 Table A-3, between lines 3 & 4 Inserted JKA, -30, 71.3, 3482, 4668, 4227, and 1847 A-9 Table A-3, between lines 10 & 11' Inserted JKS, 300, 113.0, 2529, 3636, N/A, 1
l and N/A
- i. A-15 Figure A-5 (continued) Removed data and plots of JKA and 057 and inserted 06B and JEM b
marra tu s - c o tu u su s
> a l.
Page Line ,
Changes A-16 FigureA-5(continued) Removed data and plots of JEM and 068 and inserted 057 A-18 FigureA-5(continued) Corrected JEV to JEU _ (typo)
A-18 Figure A-5 (continued) Removed data and plot of JK5 A-20 Figure A-6 (continued) Removed data and plot of JLB (bottom) and inserted JKA (top)
A-21 FigureA-6(continued) Removed data and plot of JLM (bottom) and inserted JLB (top)
A-22 Figure A-6 (continued) Removed data and plot of 072 (middle) and
_ . . _ _ _. _ inserted JLM itop) and JK5 (bottom)
FigureA-6(continued) Added new page, A-23, for data and plot of D72 A-23 --
Page numbers changed from 23 to 24 A-24 --
Pages numbers changed from 24 to 75 A-25 --
Page numbers changed from 25 to 26 A-26 --
Pagenumberschangedfrom25to21 A-27 --
Page numbers changed from 27 to 28_
i c ,
m a r r e c t s - c o c u nn e u s
i
. t '
LEGAL NOTICE This report was prepared by Battelle Columbus Laboratories (BCL) as an account of sponsored research activities. Neither the Sponsor nor Battelle nor any pe,rson acting on behalf of either:
Makes any warranty or representation, expressed or implied, with
, respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information, apparatus, process, or composition disclosed in this report may not infringe privately owned rights; or assumes any
' liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, process, or composition disclosed in this report.
i a
m arvs LL s - c o Lu m mu m
_s . .
t . _._
r .
TABLE OF CONTENTS Page 1.0 SUPMARY............................................................. 1
2.0 INTRODUCTION
........................................................ 4 3.0 SPEC IEN PREPARATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 4.0 CAPSULE RECOVERY AND DISASSEMBLY .................................... 12 5.0 EXPERIMENTAL PROCEDURES ............................................. 19 5.1 Neutron Dosimetry ..............................................
19 5.2 Charpy Impact Properties ....................................... 24 5.3 Tensile Properties ............................................. 26 5.4 Chemical Analysis .............................................. 27 6.0 RESULTS AND DISCUSSION .............................................. 29
! 6.1 Neutron Dosimetry .............................................. 29 6.2 Charpy Impact Properties ....................................... 41 6.3 Tensile Properties ............................................. 61 l 6.4 Chemical Analysis .............................................. 70
7.0 CONCLUSION
S ......................................................... 76
8.0 REFERENCES
.......................................................... 79 APPENDIX A INSTRUMENTED CHARPY EXAMIN6 TION .......................................... A-1 REFERENCES ............................................................... A-27 i
i m ar r a i. L a - c o c u m n u s
4 , 3 l
LIST OF TABLES Page TABLE 1. INVENTORY OF CHARPY AND TENSILE SPECIMENS FROM THE TWO MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE BASKETS ...... 16 i
!. TABLE 2. CALIBRATION DATA FOR THE HOT LABORATORY CHARPY IM ACT MACHINE USING A M RC STANDARDIZED SPECIMENS ................. 24 TA8LE 3. CROSS SECTIONS FOR THE IRRADIATED FLUX MONITORS (E >1MeV) IN RADIALLY CENTERED TWO CAPSULE MESHES
- . 34 (MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE) . . . . . . . . . . . . . . . .
TABLE 4. CONSTANTS USED IN DOSIETRY CALCULATIONS FOR THE l
MONTICELLO 30 DEGRLE SURVEILLANCE CAPSULE .................. 34 I TABLE 5. FLUX AND FLUENCE VALUES AT THE MONTICELLO SURVEILLANCE CAPSULE (30 DEGREE AZIMUTHAL LOCATION) ..................... 36 t
TABLE 6. FLUX AND FLUENCE BEHIND THE MONTICELLO SURVEILLANCE CAPSULE AND AT THE MAXIMUM VESSEL WALL POSITION ............ 37 TABLE 7. CHARPY V-NOTCH IW ACT RESULTS Fm IRRADIATED BASE -
- METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE i SURVEILLANCE CAPSULE ....................................... 43 i
TABLE 8. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... 44
- TA8LE 9. CHARPY V-NOTCH IWACT RESULTS Fm IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... 45 i
TA8LE 10. SU M ARY OF CHARPY IMPACT PROPERTIES FOR IRRADIATED MATERIALS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... 58 TABLE 11. . TENSILE PROPERTIES FOR IRRADIATED MATERIALS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .............. 63
-TABLE 12. CHEMICAL ANALYSIS RESULTS FOR IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO SURVEILLANCE CAPSULE ......... 72
. TABLE 13. CHEMICAL ANALYSIS RESULTS FE UNIRRADIATED MONTICELLO BASE METAL BELTLINE PLATE ....................... 74 4
11 marve to s - c o cu m nu s b
7 LIST OF TABLES (Continued) fagg TABLE A-1. INSTRUMENTED CHARPY IMPACT RESULTS FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE 1 SURVEILLANCE CAPSULE ....................................... A-7 :
TABLE A-2. INSTRUMENTED CHARPY IMPACT RESULTS FOR IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... A-8 TABLE A-3. INSTRUMENTED CHARPY IMACT RESULTS FOR IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... A-9 LIST OF FIGURES FIGURE 1. MONTICELLO CORE MIDPLANE SHOWING THE LOCATION OF THE 30 DEGREE, 120 DEGREE, AND 300 DEGREE
, SURVEILLANCE CAPSULES ...................................... 7 FIGURE 2. TYPICAL CHARPY V-NOTCH IMPACT SPECIMEN ..................... 10 FIGURE 3. TYPICAL TENSILE SPECIMEN ................................... 11 FIGURE 4. MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE CONTAINING TWO BASKETS ..................................... 13 FIGURE 5. PHOTOGRAPH SHOWING BURST OPEN TENSILE TU8E G5 FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE . . . . . . . . . . . . . . 17 FIGURE 6. TYPICAL CHARPY PACXET WITH CHARPY SPECIMEN ................. 18 FIGURE 7. TYPICAL TENSILE TUBE WITH TENSILE SPECIMEN ................. 18 FIGURE 8. MONTICELLO CORE, INTERNAL VESSEL STRUCTURES, AND VESSEL WALL GEOMETRY USED IN THE DOT CALCULATION ........... 31 FIGURE 9. COMPARISON OF DOT SPECTRUM WITH FISSION SPECTRUM AT THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE . . . . . . . . . . . . . . . . . . 32 FIGURE 10. CALCULATED FLUX (E > 1 MeV) AT THE MONTICELLO 30 DEGREE CAPSULE, INNER WALL, 1/4 THICKNESS, AND
, 3/4 THICKNESS AS A FUNCTION OF AZIMUTHAL ANGLE ............. 38 111 m ar r a s. L a - c a t u m m u s
..- 3 .
LIST OF FIGURES (Continued)
Page FIGURE 11. FLUENCE AT 1/4T and 3/4T POSITIONS AS A FUNCTION OF TIME FOR THE MONTICELLO NUCLEAR GENERATING REACTOR VESSEL ..................................................... 40 FIGURE 12. CHARPY V-NOTCH IW ACT ENERGY VERSUS TEST TEMPERATURE FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE . . . . . . . . . . . . . . . . . . 46 FIGURE 13. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEMPERATURE FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ..................................................... 47 FIGURE 14. CHARPY V-NOTCH PERCENT DUCTILE SHEAR VERSUS TEST TEWERATURE FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .................................................... 48 FIGURE 15. CHARPY V-NOTCH IWACT ENERGY VERSUS TEST TEWERATURE FOR IRRADIATED WELD ETAL SPECIENS FROM THE
, MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .................. 49 FIGURE 16. CHARPY V-NOTCH '.ATERAL EXPANSION VERSUS TEST TEM ERATURE FOR IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE . . . . . . . . . . . . . . . . . . 50 FIGURE 17. CHARPY V-NOTCH PERCENT DUCTILE SHEAR VERSUS TEST TEWERATURE FOR IRRADIATED WELD ETAL SPECIENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ......... 51 FIGURE 18. CHARPY V-NOTCH IMPACT ENERGY VERSUS TEST TEMPERATURE FOR IRRADIATED HAZ METAL SPECIMENS FR(M THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .................. 52 FIGURE 19. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEWERATURE FOR IRRADIATED HAZ ETAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .................................................... 53 FIGURE 20. CHARPY V-NOTCH PERCENT DUCTILE SHEAR VERSUS TEST TEWERATURE FOR IRRADIATED HAZ ETAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .................................................... 54
. FIGURE 21. CHARPY IMPACT SPECIMEN FPACTURE SURFACES FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... 55 e
iv m a r r a t u s - c o L u na m u s
..-+-eas-w--.m-w,*-----.
LIST OF FIGURES (Continued)
P.A!Le.
FIGURE 22. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR IRRADIATED WELD METAL SPECIENS' FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... 56 FIGURE 23. CHARPY IWACT SPECIEN FRACTURE SURFACES FOR IRRADIATED HAZ ETAL SPECIENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... 57 FIGURE 24. BASE ETAL YIELD AND ULTIMATE TENSILE STRENGTHS VERSUS TEST TEMERATURE FOR IRRADIATED TENSILE SPECIENS FRG4 THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ....................................... 64 FIGURE 25. BASE METAL TOTAL ELONGATION AND REDUCTION IN AREA VERSUS TEST TEMPERATURE FOR IRRADIATED TENSILE SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .............. 65 FIGURE 26. POSTTEST PHOTOGRAPHS OF IRRADIATED 8ASE METAL TENSILE SPECIMENS SHOWING SOTH THE REDUCED AREAS AND FRACTURE SURFACES (MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE) ...................................... 66 FIGURE 27. POSTTEST PHOTOGRAPHS OF IRRADIATED WELD ETAL TENSILE SPECIMENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE) ...................................... 67 FIGURE 28. POSTrEST PHOTOGRAPHS OF IRRADIATED HAZ METAL TENSILE SPECIMENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE) ...................................... 68 FIGURE 29. TYPICAL TENSILE LOAD-ELONGATION CURVE ...................... 69 FIGURE A-1. AN IDEALIZED LOAD-TIME HISTORY FOR A CHARPY IWACT TEST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-2 FIGURE A-2. GRAPHICAL ANALYSIS OF CHARPY IMPACT DATA ................... A-4 FIGURE A-3.. DIAGRAM 0F INSTRUMENTATION ASSOCIATED WITH INSTRUMENTED CHARPY EXAMINATION ............................ A-5 FIGURE A-4. INSTRUMENTED CHARPY IMPACT DATA'FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ............................. A-10 y
m ar v e u. s - c o L u m o u s
_ _ -.. . ._ _J
i i LIST OF FIGURES (Continued)
Page FIGURE A-5. INSTRIMENTED CHARPY IMPACT DATA FOR IRRADIATED .
1 WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ............................. A-14 FIGURE A-6. INSTRIMENTED CHARPY IMPACT DATA FOR IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .............................. A-19 FIGURE A-7. THE SIX TYPES OF FRACTURES FOR NOTCHED BAR BEND I NG . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-24 FIGURE A-8. INSTRIMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .................. A-25 FIGURE A-9. INSTRUMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .................. A-26 FIGURE 'A-10. INSTRlMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .................. A-27 l
l-1 1
vi m a r r a L L s - c o t. u na m u s
. , , . , -- - w 7,-.m- - --r--w-t---
FINAL REPORT b
on EXAMINATION, TESTING, AND EVALUATION OF IRRADIATED PRESSURE VESSEL SURVEILLANCE SPECIMENS FROM THE MONTICELLO NUCLEAR GENERATING PLANT to NORTHERN STATES POWER COMPANY from BATTELLE Columbus Laboratories by L. M. Lowry, M. P. Landow, J. S. Perrin*
A. M. Walters, R. G. Jung, and R. S. Denning November 5, 1984 1.0
SUMMARY
A 30 degree azimuthal surveillance capsule assembly was received from the Monticello Reactor. The capsule (marked 117C 3991 G-1) had been irradiated for 7.63 equivalent full power years (EFPY) and removed from the reactor after shutdown in November 1981. The capsule was visually examined, opened, and the specimens inventoried. The two baskets of this capsule assembly contained twice the number of tensile and Charpy specimens required for testing and evaluation. Each basket contained a complete compliment of eight tensile specimens and 36 Charpy specimens. One set of specimens was stamped with a combination of three digits beginning with the letter J and the other set of specimens was stamped with a combination of three digits beginning with the letter D. During disassembly it was noted that one tensile tube had burst open and probably contained two weld specimens beginning with the letter D.
- Consultant, Fracture Control Corp., Goleta, California.
m arr e c t s - c o tu u m u s
2 l
Therefore, the complete set of specimens (those beginning with the letter J) were chosen by Northern States Power Company for testing.
The General Electric Company (GE) had indicated an incomplete degree of material traceability (16,37) . Therefore, to remove any doubts, a supplemental test program was undertaken to verify that the surveillance specimens prefixed by the letter J were fabricated from the Monticello beltline plate 1 - 15 (C 2220-2, STP-1). Samples from both the unirradiated archive base metal plate marked 1 - 15, which was stored at GE, and an unirradiated Monticello archive base metal tensile specimen stamped JBL were chemically analyzed for copper, phosphorus, nickel, molybdenum, chromium, manganese, vanadium, silicon, sulfur, and carbon. A comparison of the chemical analyses indicated that for the ten elements listed, the differences were within three percent for all elements except vanadium and phosphorus.
The differences were within about 13 percent for vanadium and the phosphorus content was 0.005 1 0.001 weight percent for plate 1 - 15 and 0.009 1 0.002 weight, percent for tensile specimen JBL. It is, therefore, concluded with a high level of confidence, that the Monticello surveillance specimens prefixed with the letter J and irradiated at the 30 degree position were fabricated from the Monticello beltline, base metal plate 1 - 15 (C 2220-2, STP-1).
Four iron and four copper nautron monitor wires from Charpy packets G-2, G-6, G-7, and G-8 were analyzed. The capsule specimens received a fast neutron fluence (E > 1 MeV) of 2.93 x 1017 n/cm2 The calculated maximum fast neutron fluence at the 1/4 T pressure vessel wall pcsition occurred at about 3 degrees azimuthal. This fluence was 7.20 x 1017 n/cm2 at the time the capsule was removed from the reactor vessel (7.63 EFPY), and 9.1 x 1017 n/cm 2 at the time of the recent extended-outage shutdown which began on February 3, 1984 (9.65 EFPY). The capsule lead factor was only 0.31, which indicates that the flux at the capsule actually lags the flux at certain vessel wall positions. The end of life (32 EFPY) maximum fluence for neutron energi'es above 1 MeV at the 1/4 T position was calculated to be 3.02 x 1018 n/cm2 (assuming a reactor lifetime of 40 years and 80 percent of full power
, operation at 1670 MW )*
t Irradiated Charpy impact specimens were tested to determine the impact behavior, including the impact energy, lateral expansion, fracture appearance, and upper shelf energies for base metal, weld metal, and heat marrs cos - c o cu m nu e
- e e 3
affected zone (HAZ) metal. The tensile properties of the irradiated specimens were determined, including the yield and ultimate tensile strengths, as well as uniform and total alongations, and reductions in area.
The halves of three irradiated and tested weld metal Charpy V-notch specimens were analyzed for 10 elemental constituents including copper, phosphorus, nickel, molybdenum, chromium, manganese, vanadium, silicon, sulfur, and carbon.
Because of incomplete mechanical property data for the Monticello unirradiated materials, and especially the very low (non-predictive) capsule lead factor, material changes caused by irradiation cannot be evaluated by using the mechanical property data generated by testing the specimens from this surveillance capsule. When such unirradiated data are not available, Regulatory Guide 1.99 must be used. Therefore, utilizing only the chemical analysis results, and the 30 degree surveillance capsule fluence evaluations, the following reference nil-ductility transition temperature (RTNOT) shifts, adjusted transition temperatures, and changes in upper shelf energy for the Monticello base and weld metal were calculated as outlined in Regulatory Guide 1.99:
(a) The adjusted RTNDT was calculated to be 56 F for the base metal and -
55 F for the weld metal at the maximum fast fluence pressure vessel location (3 degree) and at the pressure vests 1 1/4 thickness (1/4 T) through February 3, 1984.
(b) The weld metal had initially been considered the limiting material.
However, because of its higher copper content, the base metal became the limiting material above a fast neutron energy (E > l MeV) of 7.8 x 101/ n/cm2 (c) The predicted maximum end of life-(EOL) shift in RTNOT (assuming 32 equivalent full power years) was calculated to be 77 F for the Monticello pressure vessel base metal at the maximum fluence
. position of 3 degrees azimuthal and 1/4 T location.
(d) The upper shelf energies for the irradiated Monticello were all above 100 ft.-lb. Using the worst case of 0.17 weight percent copper for the Monticello pressure vessel base metal, the predicted EOL upper shelf energy would remain well above the minumum EOL upper shelf energy of 50 ft.-lb. specified in 10CFR50 Appendix G.
m a r v a t u s - c o c u na e u s
' ~
t %
- 4 Further details are summarized in the CONCLUSIONS on pages 76 through 78. The data generated in this program along with the results of calculations recommended in Regulatory Guide 1.99 indicate that the Monticello
- reactor pressure vessel provides adequate margins of safety with respect to the EOL upper shelf energy and adjusted reference temperature requirements of 10 CFR 50 Appendix G.
2.0 INTRODUCTION
Irradiation of materials such as pressure vessel steels used in comercial nuclear power reactors cause changes in the mechanical properties of the material. Specimens such as tensile and Charpy V-notch are used to evaluate radiation induced changes in the material's tensile, impact, and fractureproperties.(1-6)* Tensile properties generally exhibit a decrease in uniform elongation, total elongation, and reduction-in-area accompanied by an increase in yield and ultimate tensile strength with increasing neutron expo-sure. The impact properties as determined by Charpy V-notch impact tests gen-erally exhibit an increase in the ductile-to-brittle transition temperature and a drop in the upper shelf energy.
A reactor pressure vessel receives neutron irradiation during operation and as a result is subject to radiation-induced embrittlement.
Because the reactor pressure vessel contains the reactor core and coolant, the changes in fracture properties must be known. Therefore, a pressure vessel surveillance program is required by the U.S. Nuclear Regulatory Comission (NRC) and material surveillance capsules containing appropriate specimens are placed into each comercial nuclear power reactor prior to initial startup.
The purpose of the surveillance program associated with each reactor is to monitor the changes in mechanical properties as a function of neutron exposure.
The Northern States Power Company has a surveillance program for its Monticello Nuclear Generating Plant which is described in reports issued by i the General Electric Company.(7,16) The program is based on ASTM E185
" Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels",(8) and was conducted using numerous other
- References are listed at the end of the text (pages 79, 80, and 81) m arre c t s - c o tu m s u s
5 American Society for Testing and Materials (ASTM) and American Society of Mechanical Engineers (ASME) standards.(9-15)
Three surveillance capsules, each containing Charpy and tensile mechanical property test specimens and iron (Fe), copper (Cu), and nickel (Ni) dosimeter wires, were inserted into the reactor pressure vessel prior to the initial startup of the Monticello Nuclear Reactor. Figure 1 shows the s position of the three (30, 120, and 300 degree) capsules.
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Appendix G for Nuclear Power Plant Components, Division 1 presents a procedure for obtaining allowable loading
-for ferritic pressure retaining materials to protect against nonductile failure. The procedure is based on the principles of linear elastic fracture g mechanics and is related to the reference nil-ductility transition temperature The current ASME code (12) and the code of Federal Regulations (13) requires that-the adjusted RTNOT(initialRTNOT plus shifts due to irradiation) must be less than 200 F and the Charpy V-notch upper shelf energy must be at least 50 ft-lb. RTNOT is defined in reference 14, and is the l higher of the nil-ductility transition temperature (TMDT) determined by drop weight tests (15) and the Charpy V-notch test temperature (TCV)minus60F.
T must not exceed (TNOT + 60 F) and be that temperature at which three CV
- Charpy V-notch specimens exhibit not less than 50 ft-lb absorbed energy and at least 35 mils lateral expansion. Thus the reference temperature RT NDT is the higher of T NDT and (TCV - 60 F). Tests of base metal, weld metal, and HAZ
( metal ~Charpy V-notch specimens should be conducted and the highest RT NDT used l to calculate the reference mode I stress intensity factor K IR. Startup and l operation curves are generated based on the calculated KIR. At the time of-l initial operation of the reactor, the pressure-temperature operating curves l were specified. During the life of the reactor, the curves are to be revised i
to account for the changes in the Charpy impact behavior of the pressure vessel material due to irradiation. The adjusted nressure-temperature 3 operatirg curves then allow for safe hydrostatic pressure testing, startup, l and operation of the reactor.
A previous report covers the preirradiation baseline tensile and Charpy impact properties of the three materials from the Monticello i
sarv e 6L s - c o cu m nu s
- L.
~ ^
_- - _-= .- - . - _ , _
i . , -
6 l
reactor.(16) It should be noted that, since there had been insufficient tests
- and data, the initial RTNDT values had to be estimated analytically.
- The present report includes descriptions of the recovery and j disassembly of the Monticello 30-degree surveillance capsule and the examination of the test specimens and dosimetry wires. This report also l includes the procedures and results of the tensile and Charpy impact tests and I dosimetry and chemical analysis for the Monticello 30-degree surveillance capsule which was removed from the reactor during November of 1981.. Based upon the Charpy test data, chemical analysis results, and neutron fast fluence evaluations, an adjusted RT NDT and drops in upper shelf energies were calculated in accordance with the procedures of Regulatory Guide 1.99 for irradiation through February 3, 1984 (the date the Monticello Reactor was shut down for an extended outage).
The BCt. surveillance capsule quality assurance program is a plan-ning, contro111na, surveillance, and documentation program to assure that all work is, conducted following the basic orinciples of scientific investigation.
The organization of this program follows the requirements of Title 10 CFR Part 50 Appendix B, ASME NA-4000, and ASME Section III M8-2360, " Calibration of Instruments and Equipment", where applicable to testing verification. All tests were conducted in full compliance with the Nuclear Materials Technology Quality Assurance Manual. This manual is responsive to all 18 criteria of a quality assurance program.
Implementation of the qualitv ass"rance requirements included the use of technical and quality assurance authorized work instructions, procedures, and work completion forms. The forms were used to document that all data was generated in compliance with the procedures and conformed to requirements of the applicable ASTM specifications. Both Charpy and tensile machines were periodically certified to ensure accurate and reliable results.
A system of technical overchecks and independent quality assurance surveillance was used to insure compliance with the procedures and the overall quality assurance program. All personnel were trained and certified in i compliance with ANSI N45.2.6 as being tecnnically qualified for the task being undertaken and were aware of the quality assurance requirements.
All data-generating instruments and apparatus were calibrated by standards traceable to the U.S. Bureau of Standards.
m a r v a t i. e - c a s. u na m u s
i a
/
7 core Pww ry stamiens steel shroud o' 30 Depee Jet Pump ////// cm,suse neester Pressw vesse - - - -
1/s-inen seemies.
stees uner
-% ~~~.
,- . . , . :~
capsuse f
7.:..
- - + s
.+ . + +
/
\
I g 1- , s + + ,
, + + .s s
\
/ I ** '\
/ I' + t ', N /
< 'h 8 ' i m* -- - + m*
+,
h \.
\
\ '
+ -
. . ,5I l
3 ,
./ I
\_ 4 . i .
\ /
y + . . 4
.L e
- 4 =/
\
s . , ,/ '
s s.
s s
-/
\ ,
'7 ~_7 120 Deerm m _
~
/// f//
100*
, FIGURE 1. MONTICELLO CORE MIDPLANE SHOWING THE LOCATION OF THE 30 DEGREE, 120 DEGREE, AND 300 DEGREE SURVEILLANCE CAPSULES e av v a i. e. s - e o n. u m n u a
~ ~~ '
_____T_-_
8 Specimen receipt and the packaging and shipment of wastes for dispo-sal are in accordance with the quality assurance program which is responsive to Title 10 CFR Part 71, Appendix E. All waste material from the capsules was disposed of in containers authorized by the applicable Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regulations at a properly licensed waste disposal site. Mechanical property specimens and dosimeter wires are being held for 12 months following receipt of this final
- technical report by the Northern States Power Company.
3.0 SPECIMEN PRE'PARATION The Monticello reactor pressure vessel was purchased from the Chicago Bridge and Iron Company, Birmingham, Alabama.(16) The vessel was designed and constructed in accordance with the ASME Boiler and Pressure Vessel' Code - Section III,1965 Edition with addenda to and including Sunener i 1966 addenda in accordance with the General Electric APED specification No.
21A1112, Revision 6. Base metal specimens were cut from flat slabs cut
- parallel to both the plate surfaces at a depth of one-quarter- and three-quarter-plate thickness. The Charpy and tensile specimens were machined with their longitudinal axes parallel to the plate rolling direction. The Charpy specimen notches were cut perpendicular to the plate surface and designated longitudinal specimens.
The Charpy weld metal specimens were machined in a direction trans-verse to the weld direction; thus, only the central notched section of the specimen would necessarily be composed of weld-deposited metal. Charpy specimens were taken throughout the weld section to a depth of 0.75 inch from the weld root. The Charpy weld metal specimens long axes were, therefore, parallel to the plate surface, and the notches were cut perpendicular to the plate surface. The tensile weld metal specimens were composed entirely of weld metal and were obtained by machining the specimens parallel to the weld length and parallel to the plate surface.
SATTELLE = C O LU M e u s
L
. e i 9 -
The Charpy weld HAZ metal specimens were machined in a direction transverse to the weld length and parallel to the plate surface. The axes of the notches were then cut perpendicular to the plate surface, with the notch located at the intersection of the base metal and weld deposit. The tensile weld HAZ setal specimens were machined transverse to the weld length and paralln1 to the plate surface. The joint between the base metal and weld deposit was located at the center of the tensile specimen gage length.
A modification of a marking system developed by the U.S. Steel Corporation Applied Research Laboratory (designated FA8 Code) was used to mark one end of each surveillance Charpy and tensile specimen for later positive identification.
The Charpy V-notch impact specimen design is shown in Figure 2.
This is a standard specimen design reconnended in ASTM E23-82 entitled
" Standard Methods for Notched Bar Impact Testing of Metallic Materials". The tensile specimen design is shown in Figure 3. This specimen design conforms to recommendations in ASTM E8-81 for small-size specimens. The ASTM E8-81 standard is entitled " Standard Metheds for Tension Testing Metallic Materials".
i m arv s o u s - c o tu m o u s L_____.______.______ ._ _ _ _ _ . . _ _ . _ . _ _ . _ _ _ - . . _. _ . . . _ _ . _ . . _ _ _ . _ . _ . _ _ . _ _ _ . _ _ . . _ . _ _ _ _ _
,. ., , - 1 10 i l l
2.001 63
.010 R.
--> c a a3 lilcl.00il
/ Tr/
/
I -c- 1 L I .315 1
9 L +
DetsN 8 110 1 l A l .001 l
.- y1
- 7 r 2.001
! \ " l-A-l w m 1r 3 llll Al .001 l 1001 ~ 304
- 1.G42 :
LH1
' 2.186 :
l .
FIGURE 2. TYPICAL CHARPY Y-NOTCH IMPACT SPECIMEN 1
BATTELLE - C O Lu m g u g
- ~ ..
s ,
11 A375 - 14 UNC - 2A
$ A@ .005R @ e.1,;;;; *** :
Both Ends Gage Length j Light Priek Puneh
/ Gage Marks 2.0s 2.02 see
- 88-*
-Note -See Note 2
-___. u 4 /
/ n b k-FP-< h D' l +
~
iS* e. 83
. .375 R.
, 30 2.02 102 MI:1.
2 Pleses eM : ; 1,;;;; 2 Places 2 Places 1.290 Min Reduesd Section
- 3.00 :
Notes:
- 1. D = .250**#1 die. et conter of reduesd section. D* = estuel D die. + .002 to .006 at ends of reduesd section tapering to D at conter.
- 2. Grind reduesd section and rodii to y rodii to be tangent to reduesd section with no skeuler tool marks at point of tangency or within reduced section. Point r.f tangency shall not lie within reduesd section.
FIGURE 3. TYPICAL TENSILE SPECIMEN 1
savva LL s - c o Lu m ou s
- ~~
t____________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
4
[ T I 12 ,
j- CAPSULE RECOVERY AND DISASSEMBLY I 1 i i l The serve 111ance capsule assembly was shipped from the Monticello j
- Reactor site to the Battelle Columbus Laboratories (BCL) hot laboratory for !
4 postirradiation examination. Upon arrival at 8CL oa February 2, 1982, the j assembly was transferred to a hot cell for visual examination, serial number f' verification, photography, and disassembly.
l The initial visual examination revealed two notable features. The l first and most obvious was that the capsule contained two baskets (see j Figure 4). From these photographs, it appeared that each basket contained four tensile tubes and three Charpy packets for a total of eight tensile tubes and six Charpy packets. The second and less obvious feature was what appeared to be a burst-open tensile tube. The dark jagged edge of the burst-open
- tensile tube can be seen through the hole in the containment basket indicated by the arrow in Figure 4. After disassembly the tensile tubes and Charpy packets were again examined. The lower basket bore the serial number
, 117C 3911 6-1. Both baskets bore the Mor,ticello Reactor code number 19. Both
- j. were stamped with the basket code number 1, which corresponds to the
- -applicable group number, and is the same as the last digit in the basket 4'
serial number. The Monticello Reactor code number and basket code number j appear as a binary code, and it is explained in Reference 7. The binary code numbers (drilled holes) appeared in the lower corners of the basket surface,
- facing the pressure vessel wall (back face) and the serial number (stamped
- alphanumeric) appeared in the lower center of the basket surface facing the core (front face).
Both baskets were opened by cutting away the lower (spacer packed) ends using a flexible abrasive cut-off wheel attached to a Mototoo1*. The upper basket was opened first and contained four intact tensile tubes and
.three Charpy packets. Identification numbers of the tubes and packets are
! listed below in the order of their location with the first being located
- Mototool is a trademark for a variable, high-speed motor attached to a i
flexible shaft and chuck for grinding and cutting operations.
i i m ar v e L L s - c o c u na e u s i
~ - ., , ,, .. . -
13
(
w y7;-
Y h '( _j L- @ b % O O- 4 L L @d '600- 1 OLU_
^
1 W O tb
?OLtC '9 9 63-
]3 0.3X C-9639 and -9640 CAPSblE BACK SIDE *
~
l*
,g ? . . , . - ;..._._
,; % ,.,.. .. . .i s. - . . . < , '
~ :'
= 3.,
f, .. _.; .-
' ~~. ;p, ' " '.
,e .; T.: 3; p . . . .
- 4. s . . # ;. .
{l .1-* r . s.;m ..e.?.
-: .t , :l3, . ..:l .'> ',. f 3. :. _ ,- , ' ) ,, ,.
- ;'q'. . 951e -
.s. q 7 ~ n.-
F .~
lYJl:-l;l.,L.j,Y~l.?-l,1'~ ' ~ ; }; ; , . y. ^j;. .
, 4
- 3
. e. . . .
.:p.-
3s
..e ;......
s, -.
- .. ~.L,
?. ' ' ' . ' . ; ; s ., *- ,.
- v A ^*. L'
^* '
[ ': , Q :' ,-ysy S 'c.1: Q * .
~f V; .. .,
.~
f n M . -' : .'. f 'g I , t .. .
,?--
% y v.'!:.$. .,;, ' ;- ( , b:.Q .~ P(j
- '. . ; ~kl,d'o ~
~ ~
'N i *[7'.<d'
, . ..;~ ;./%'y'?[.
.. ..f ..c ,- '.k.;: -[%:..
{ . ,W.
t_ _ . g 3,:
~-
1:.4 . .
[-
( ., yl ;-.v" __ Qp ._ ,
- I'. *< %. q. ,., : y . g
.r* . ? -% h;; ; _ _'-I . .. ., ; 'y : ' ~ % 4 . .W -
'W i y .., ' ~ - ;,f.' i "
fy.1 _., :,m ., y; ,,
y 5_.L. * < , .. ,
.a' n .. F
, .N 'l_..Y'.-'.l,.- .._s.. s. -. C y . .. . E *' .4.? _. . -.m
0.3X C-9634 and -9635 _
CAPSULE FRONT SIDE *
- The capsule front side was facing the core and back side was facing the pressure vessel wall.
FIGURE 4. MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE CONTAINING TWO BASKETS m ar r e t t a - c o cu m n u s
, e ,
4 14 I'
t' i at the top of upper basket and the last being located at the bottom of the i upper basket. The Cha:py packets had both the binary code numbers and the j alphanumeric identification, whereas the tensile tubes contained only a letter and a number stamped into one end of the plug.
l Charpy Packet 6 117C 3913 G-6 Tensile Tube G6 Tensile Tube G8 Charpy Packet 8 117C 3913 G-8 i Tensile Tube 69 Tensile Tube G10 Charpy Packet 7 117C 3913 G-7 e
, Upon consulting with Northern States Power Company personnel, the decision was made to open the second basket. Identification numbers of the tubes and packets are listed below. .The list is in order of their location, with the first being located at the top of the lower basket, and the last being' located at the bottom of the lower basket. Again, the Charpy packets had both the binary code numbers and alphanumeric identification, whereas the l tensile tubes contained only a letter and a number stamped into one end of the plug.
Charpy Packet 1 117C 3913 G-1 Tensile Tube G1 Tensile Tube 63 Charpy Packet 2 117C 3913 6-2 Tensile Tube 64 Tensile Tube 65 Charpy Packet 3 117C 3913 6-3 n
eavvatus-cocumous i
i .
1 4
15
- The six Charpy packets were also opened using the abrasive cut-off wheel to remove one end of the packet. The specimens were then removed by shaking the packet and allowing the specimens to drop out the open end. Each Charpy packet contained one iron (Fe), one copper (Cu), and one nickel (Ni) h dosimeter wire. An inventory of the Charpy specimens is given in Table 1, and a total of 24 base metal, 24 weld metal, and 24 HAZ metal specimens were recovered.
Seven of the tensile tubes were opened using the abrasive cut-off wheel to remove one end of the tube. The specimens were then removed by shaking the tube and allowing the specimens to drop out the open end. An
- inventory of the tensile specimens is also given in Table 1, and a total of j six base metal, three weld metal, and five HAZ metal specimens were recovered.
It was noted that the tensile tube G5 appeared to have burst open, i
as shown in Figure 5. Note that the tube burst in two positions, near the
- center,of the two tensile specimens. It is unlikely that the burst occurred j simultaneously and, therefore, it is postulated that the following sequence of l
events occurred: (1) the tensile tube G5 was not sealed during fabrication or a leak occurred after insertion into the reactor; (2) water leaked into i
the tube and reacted with the contents (oxidized the iran and aluminum) and an effective gas tight seal was formed at the center of the tube producing two l compartmentswithinthetensiletube;(3) hydrogen pressure produced from the water / metal reaction c ased both compartments to burst open. After again con-sulting with the Norther) States Power Company personnel, this tenstle tube 65, along with the two contained tensile specimens, were discarded as waste.
A photograph of a typical Charpy packet is shown with a single Charpy impact specimen in Figure 6.- Similarly, a photograph of a typical tensile tube is shown with a single tensile specimen in Figure 7.
l l
. m ar v a t u s - c o L u na m u s
16 TABLE 1. INVENTORY OF CHARPY AND TENSILE SPECIMENS FROM THE TWO MONTICELLO ~.
30 DEGREE SURVEILLANCE CAPSULE BASKETS (" FAB" CODE)
Charpy Packets a
G-1(a) G-2(b) g_3(c) G-6(a) g.7(b) G-8(c)
D3M D6A DBT JDJ JEM JKM Dic 05C 072 JDA JEK JKK -
D3P DSB -
07E JD5 JEY JLM -
03E D57 DBU JDU JJT JKT ..
02L 051 076 JE3 JE7 JK5 03'3 052 DAE DES JEL JLK D3Y 053 077 JCP JJ7 JKD 037 055 07A JD1 JJP JKA D3A 056 D75 JD4 JEU JL2 035 05A 074 JE4 JJM JLB D34 D6B D73 JDY JJE JLE D36 D5Y 071 JE1 JEP JLC Tensile Tubes G1(a) G3(c) G4 G6(a) G8(c) G9 G10 1 DC2 DE2 JC1 JCK JC6 DC4 DE3 DC5fl DDC JC2 JCM JBMfl JB2 JB6 i
a) Base metal specimens b Weld metal specimens except as noted c HAZ metal specimens except as noted
,SATTELLE - C O LU M B u s
~
um .-
1, a e l
i
'l 17 t
1 4
S
, n t..
y \
.: m' -w.
-.y ,-
- . , p, . :ee p _
a ,a, 2 s ,' c .J. ..
. ,: .t. . '
,. 5 .; g. .. s.9 s,.
j
,'*J vf. C.3,s ,,
, s u
, - - . Y..--,' .
y .k, .h. h . , '4,..).'-'; t.- - [ .,' .
1 c* . !% k. .-' : ,p > .. ;. . , m- ' , .
9"...d : ". d, 4..'.
~'- <, . .
..a .. u .. -
( .p,, '"' , A, p?. -- ~ ...,.:
,,,p..,..'
. , . r'- . . . - . ' '"
+ --
.;f 3
',f.:
i '
y l *Q.:' '. Q,, &,;i.O " h' .: '.. ' ' l < M W l: . ;x ,L
( .c .s vg.....y,~ -.
- c i
..,_. '.[. -
s-A .z g~ %%.$45:M', ,;;. f. f i 4 ff' ,,
r: u y* 4:!.' yyi.)f.,, S + . ,.-a. );f)i. f
. ; ;g 3_ .. ,'y.,..
. p ., ( .; .,' -% " , - .-
4 ; ;
. , g/ e ' r
- x&p . .-
?p
'. ,,_..J..?.
y ,
. . ; r ' .. .,8
~U*-
',- r
...,,A .w \.s.
. - ,a
., f.
- ;-. .4
.-.& . n. 4 .,.s.. v 3,
. 1
.,,y.=..,M,<.* ,,
0 - ep * ?. -
.- ~ + . + . .
. , . . r.- ....'.~-+ , ,o k'4 , . . , ' ;t . .. f'- l$ _ r f, 'g>..'
~ . C. '. ., .;' . .' r ,) ~-
fth ': . -.j n-.....
4 1
< ,9>*x* 4., u,
. %%/ . . .
?. - - - >.
s4 ' %..~ . *-- ;
- , . ,i , z .. ,.., 3
.q. ,.
.j;- , l g - j d.-
. ,. ;' :' * ,, y . k *f* y/ , f
=4g v.w.
,.";'j,7: _ r , ..g,_
, ..; ;s %&V
.w,!. [,p,4 -Q:p. .,
- ;, . g. .. .. , , , -
'. ? -
& < u '. G y- 9' . .< .s
.~
1 2X C-9637 2X C-9636 l
l
.I wm-Td;I -,,.n-
, V.j. ' ~ l ' 3. L
- <..'. ' . ' , cy I y
?b
\ l %*
%rn."
< -. . Ds n
4
- S ',S, 3, .,2,k .- ~-
.- {
I
' ~
....:..y a ,.o.
' ,:1: y ,1 f L :
- .M.$v, adY y't%??. ~;M :. .
- .vw
~ l R'ii
' ' .$.$.w, N 3 :6. . w, ~
, .,, ..x.A ;1 . - u >
7 5' W.i.f't' s ws w ., . .'.m--
+
i %c.*M L s. .. . .I . . . . a .; w . n ~ ' : ?n . ., G ,,u i :- L. , . a .a 1x C-9828 FIGURE 5. li PHOTOGRAPH SHOWING BURST OPEN TENSILE TUBE G5 FROM .
THE MONTICELLO 30-DEGREE SURVEILLANCE CAPSULE i .
t i
1 SATTELLE -COLUMSUS .
e
. s ;
- - - - ,,.,_,m. . . _ ., - _ _ - . . . . _ , , , - , _ . _ _ .
i a 18 u ;,* & n ..
j }? 3 ,y,' t . C .i e 7 . .
g*2
<- 9 e 3 , vi ,4 , y. . .,. , .,..~,-;..
- ,4j,t, .. . .
.. p' , ;, , ,, -
. r 4L s. .
, :1 e M.
. ):,
. . '[ _ . y<. . ,# .y s,%.g.- % .a.
.k - g .
y
'- - g 4. ,'3 t. :k'# l. $
S p,, . . ' - [M p w
4.,.,.p .;l.m ,g+ M, . ' . 3
- ,- .. : v -
- a. ,, -C'
.. J g .& . ' ' . . , ,'!' ~- -%.'%s _ y' ' , Kr ." D ., f,.-, . , '
u ... i' sd i- 1 .t - - .. + T
.n ' ,- k ,~- .
. . < *e . , ' ' -
,- N " e. [ 6 '.) ':J y , cy ? f Y.i., . . . ,
--< [;. .?..
i 7- . >.i@.
, - , , u, a:, r. . - -
Y 3N['"f. . r.-..q
_, 4
- [ .,4 p,
y a
- g' a
W* ,
g., .-,
- y
~.~ ..
, ,...3, y, : .-<. . , ' ' , '
l . -, .. . - [k l.',~'). .L N .% . ' , '- b _ ',_( '
- .. sy
- ,cj ~- ' .-
t '
t..
. ' i,1
^
. m. -:,, ,[,0 *N- # i 1
_%* *f :
. . y, ... *: . - p ' . 'yp s.4. $ c.
,. . . - -, .i. , ,,, -
s
. , .. - v. a. . ..;
1V -
s, C. J; _ . / . 2 ' s -
. . [? -[.f * '.p_ .
- J _}.%:. : V Q
5.* . %.
- A . ^. ).r., ' - g n .
- t. 4, (> .f . M .].. m. c
,- -) ,?. . . . . . .- , . . ;.;: 4 ..; ,-.. -.. '. .
s f. - .. ;
.' .g'. s . . .i w.. <
w a ~ t- $. -
.g '. . ,g a, i .. %
p ,. , ,, s. .l- ,; - - .- Y1 3. , -
' i'*' . .p 3-
'l ,, ,-'" N .,% .].hf, g. ', ,
i y' . . , . +- , I. g MA" 1 '/ g
,- ', . j . .
' 4,
}.* / f . i[h - % . h. [_^k. * ~
.- ' . . ' , I .? 7 , '-f[ q ' 1 'g,- ,[#". . . . .[ 2 f ; F, .-[*'* - *c i
,, 7 J, ' T, f' ,.
- - - [j,-9, '. - - '3
- >q .
J , ;, j q g' . .I 7.; E #i,. , ,. %,
W._;* ~,&, :. ' g.:, ;q . . } ' "
j *( ~ ' ', . " . .
-[, .< d
, . . L *;'_ ' '.i - >}, :. '- .~l
'. ' .
- t. T ;. ~ f. * ' ., *
.., _=,',,
. w __;3 , ,G
. .b t: ?..'
.g ;, 4.g.' p. 5. .q- .e -
- u. ...
% v .-
<c, -
vy
,= . , ...
. r .- -;,( .-
.j e . . '..
- 4. .. m- g .y ; ,, 4, , ,, ,..,*.w. - =. . #. t ..*7.. ,-.. , v. ,e,.
. . , .~n 5.--
. n..- _.. . . _ .
2 v.;-.. .u. < , ^ - v . , .
/; " p. }. y.
- L -
[ e y ', ., . T.J :.-. ,:.. s a.
.g 3 ,-- . .
m ' ' , ,v.
Q $ : ;,. . ' .4 ,,Q,ff. .
)x 7 2 . ..y : ,, . .:. .
y.,. = ? '%u a .
.s> $@- C-1681 c kW*t: 1%=s,w&_s% - -*~
.% ~y- w,arw m a a ,
FIGURE 6. TYPICAL CHARPY PACXET WITH CHARPY SPECIMEN
~
- j. . . . . . . , . .
)yli ;, , ,N
. '{ . .k k.S[,[ ' . (.~k -
,]f e.. ,. t, f (*;. y '. 1,, -
- t. - 4 . ,- , ,- ,,.,,- .c.,,, ,
. s, wb Ty,, .,. ..: ,. .a.
3, .
f .
. - t . c,. . ,i.,.',..a,,
A.. . g. - _
- sc .s.
. ) ..
.y4y,,$.., , . ?. . - . . . A, yr .. ?- 4. , - w.
,..,<3.g s.
g # <
,..,e.,
' . 3.c. L , , , , ,y.; .., , ' . - ,:s
.3 -
v w
. s t+
,o ' - ' ,
9 g
?
A L
l' f
A c .
(. s. . ,.
4
-.c, .. y =
.o m,,- , .._., ..
,3
,, .,g .
15%j,.
e f^. + A4 -'~ T , b. 7'9.]. 4- . ;; ,
.. _ . , .,.m . - -
w-a IX C-1680 FIGURE 7. TYPICAL TENSILE TUBE WITH TENSILE SPECIMEN 8 A T T WE L L E - COLUMBUS
--mens----um -s - -i e
. 19 5.0 EXPERIMENTAL PROCEDURES This section of the report describes the general procedures used to determine the neutron (>0.1 and >1.0 MeV) flux and fluence and to determine the pressure vessel material impact and tensile properties. The general procedures for chemical analysis'are also included. All tests, except those for carbon analysis under Chemical Analysis, were performed at Battelle's ColumbusLaboratories(BCL). All data evaluations were performed at BCL and the original data are recorded in Laboratory. Record Book 37550.
5.1 Neutron Dosimetry
, Each of the two Monticello surveillance baskets contained three Charpy specimen packets. The flux monitor wires, one each of iron (Fe),
copper (Cu), and nickel (Ni), were recovered from inside each of the Charpy packets. Each wire was identified, placed in a plastic vial, brought out of the cell, ultrasonically cleaned in a water / soap solution, placed in a clean vial, and transferred to the radiochemistry area for further cleaning and analysis. The wires were cleaned by wiping using successive swabs containing j dilute acid (10 volume percent nitric fof Cu and 25 volume percent hydrochloric for Fe), distilled water, and reagent alcohol until a negligible contamination level was reached. Because of the short half-life associated with'the 58Mi (n, p) 58 oC reaction (71.2 days) the nickel dosimeter wire were not counted and therefore only the iron and copper dosimeter wire data was generated.
Depending on the wire activity, a suitable'and representative sample was selected for counting. Four Fe and four Cu dosimeter wires from Charpy packets G-2, G-6, G-7, and G-8 were weighted to an accuracy of + 0.0001 g T using a calibrated (NBS traceable) analytical balance. The eight wires were then mounted and analyzed by gama ray spectroscopy. Fast neutron flux and
~
1 m arv a t u s - c a 6u m m u s e a
20 fluence values with energies greater than 0.1 MeV and greater than 1.0 MeV at the capsule wall, 1/4 T, and 3/4 T locations were calculated. Data used in these determinations included the followirg:
Dosimeter Threshold Material Reaction Energy. MeV Half-Life Fe, pure 54F e (n, p) 54Mn 1.5 312.6 days Cu, high purity 63Cu (n, a) 60Co 5.0 5.27 years The ASTM procedures followed in the measurement of the monitor activities and calculation of the neutron flux included: j ASTM E261-77, " Measuring Neutron Flux, Fluence, and Spectra by Radioactivation Techniques" ASTM E263-82, " Determining Fast-Neutron Flux Density by Radioactivation of Iron" ASTM E522-78, " Calibration of Germanium Detectors for Measurement of Ganna-Ray Emission Rates of Radionuclides" ASTM ES23-76, " Measuring Fast-Neutron Flux Density by Radioactvation of Copper" ASTM E482-76, " Application of Neutron Transport Methods for Reactor Vessel Surveillance".
The BCL premium, high resolution 50 cc high-purity germanium detec-tor, capable of 2.0 kev resolution (full width, half maximum at 60Co 1332 kev peak) was calibrated with NBS standard reference materials and was used to determine the radioactivity induced in the flux wires. Data handling and reduction were accomplished using an Ortec Model 7010 Multichannel Analyzer (4096 channels).
The integrated neutron fluence at the surveillance location was.
-determined from the radioactivity induced in the irradiated detector materials. The gaena radiation from the dosimeter was measured and used to calculate the flux required to produce this level of activity. The fluence was then calculated from the integrated power output of the reactor during the exposure interval.
marva to s - co Lu m mu s
21 The activity A induced into an element irradiated for a time ti in a constant neutron flux is given by:
A = N[ c(E) * (E)dE](1 - e- *i) o where o(E) = the differential cross section for the activation reaction (barns)
- $ (E) = the neutron differential flux (n/cm2 /sec)
N = the atom desity of the target nuclei (atoms /g)
A = the decay constant of the product atom (sec-1). If the sample is permitted to decay for a time tw between exposure and counting, then the activity when counted is-1 A = N[ o (E) $ (E)dE](1-e- Ati) e- Atw I
If it is desired to find the flux of neutrons with energies above a given l
energy level, Ec, the cross section corresponding to this energy level is 1 defined as:
o(E>Ec ) = [0 o(E)$(E)dE
$ (E)dE where
$ (E)dE i $(E>Ec)=[Ec l
m a r v a t u m - c o t u ma n u s i
j
22 Then (E)+(E)dE -
o(E)$dE =
0
[ c $(E)dE J Ec $(E)dE
= o(E>Ec)$(E>Ec) and the activity A may be written as:
A = N a(E>Ec) +(E>Ec) (1 Att) ,-Atw ,
l
!' The flux is then computed from the measured activity as:
A
, $(E>Ec)= .
N o(E>Ec) (1 Atj ) 8-A tw
^
i To correct for fluctuations in power level, the flux is computed as:
A
$(E>Ec) *
, No(E)Ec)C where C= fn ( 1 - ,- AtY ) ,- At" n=1 '
N = number of time intervals of constant flux f n= the fractional power level during interval n
~
i- tn = the time length of the interval n irradiation i
tn = the time between the end of interval n and counting.
w m a r r a s. L a - c o t u m m u s w= , w
____-_-___m.__.. ____-_-__m_ _ _ _
o I 8 23 In order to determine the effective cross section to be used in the above calculations, the cross section as a function of energy must be known and the neutron flux intensity as a fur:ction of energy must be known. A cross section library of this nature is ava11able(18) and a computer code SAND-II(19) was used to retrieve the cross sections desired from this library. The neutron flux and spectrum was calculated with computer code DOT.(20) This code solves the two-dimensional Boltzmann transport equation using the method of discrete ordinates. The reactor geometrical configuration design was modeled to simulate the core structure, intervening structures, and pressure vessel. .
Calculations were performed in the SgP3 approximation using 22 neutron group cross sections from the DLC-23 library.(21) The effective cross sections were generated by the DOT calculation. Coincidental with the calculation of the effective cross sections in the DOT run, the lead factor and neutron flux profile in the reactor vessel wall were also determined.
The neutron fluence was calculated by multiplying the flux (neutrons per square centimeter per second) by the time of operation at full power (using effective full power seconds). To perform the computations, the following information was used:
(1) A description or sketch of the fuel bundle arrangement making up the core, the structures between the core and the pressure vessel, and the pressure vessel itself. This description included materials, thicknesses, and distances between com-ponents. The cladding material properties and thickness was also incuded.
(2) The average fast flux distribution in the core. These data included the fuel bundles in one octant of the cor6 and covered the entire time span during which the capsule was in the-reactor.
(3) Detailed capsule and capsule holder drawings and the exact position of the capsule relative to other structures.
(4) A complete energy generation history by month (MWHt per month) i for the time during which the capsule was in the reactor, plus a value considered to be full power.
m ar v a t i. e - c o c u m n u s
24 5.2 Charpy Impact Properties Charpy impact tests were conducted using a 264 ft-1b Tinius-Olsen Model 74 impact machine in accordance with ASTM specifications.(11, 22) The 26A ft-lb range was used for all tests. Velocity of the hanner at impact was 16.87 ft/sec. Calibration of the machine was verified as specified in ASTM E23-82 and proof tested using a set of standard Charpy specimens obtained from the U.S. Arigy Materials and Mechanics Research Center (AMRC) of Watertown, Massachusetts. Results of the proof tests are listed in Table 2. ,
Instrumented impact tests were coiiducted utilizing a tup (hasser) on the impact machine to which strain gage instrumentation had been added. The instrumeated tup in conjunction with a computer controlled, progrannable system and a digital storage oscilloscope to record the load-time history of eacn impact test was used as the data acquisition system.(23) The information stored in the oscilloscope was then recorded using an X-Y plotter to produce hard copies of the test load-time curves. Testing of the irradiated Charpy V-notch specimens from'the Monticello capsules followed in general the recosamendations of the General Electric document SIL No.14, Supplement 1.
TABLE 2. CALIBRATION DATA FOR THE HOT LABORATORY CHARPY
, IMPACT MACHINE USING #ettC STANDARDIZED SPECIMENS l
AMRC Average of 5 Standar Variation Between BCL Average BCL Energy Energyta(l And MettC Standard Eneray Group (ft-lb) (ft-lb) Actual Allowed Low Energy 14.1 1 0.4 14.6 -0.5 ft-lb 11.0 ft.-lb High Energy 73.7 1 2.7 72.5 +1.7 percent 15.0 percent i-(a) Established by U.S. Ariqy Materials and Machanics Research Center.
marvs L L s - c o cu m nu s
a a a
i 25 l ASTM procedures for specimen temperature control were utilized.(22)
The low temperature bath consisted of a refrigeration unit containing methyl alcohol. The alcohol was agitated by a magnetic stirring bar to minimize temperature variation in the bath. The liquid level of the bath was maintained so that a minimum of 1 inch of liquid over the specimens was maintained. Each Charpy specimen was held at temperature for at least the minimum time (+ 1 C for at least 5 minutes) recomended by ASTM E23-82. Tests above room temperature were conducted in a similar manner using a heated oil bath.
Each specimen was fransferred from the temperature oath to the anvil of the impact machine by an automatic transfer device. Specimens were removed from the bath and impacted in less than 5 seconds as the testing proceeded.
The energy required to break each specimen was recorded and plotted as a function of test temperature.
Lateral expansion was determined from measurements made with a lateral expansion gage.(22) The amount of lateral expansion as a function of test temperature was also plotted. Fracture appearance (percent shear) of the l
Charpy specimens was estimated from observation of the fracture surface and by comparing the appearance of the specimen to an ASTM fracture appearance chart.(ll)
The Battelle's Columbus Laboratory approach was to test each type specimen (base, weld, and HAZ metal) in the approximate temperature range of
-50 F to 400 F with the actual test temperature mutually agreed upon prior to testing. The data generated was used to construct conventional Charpy transition curves, which were could then be used to determine the adjusted referencetemperature(RTOT). N Emphasis was placed on establishing a 30 ft-lb, 50 ft-lb, and 35 mil lateral expansion index temperatures. Because
- of the current concern regarding the upper shelf energy level of pressure j vessel' materials, tests were also conducted in a manner such that the upper shelf was well-defined. Items reported include test temperature, energy ,
absorbed by the specimen in breaking, lateral expansion, percent ductile fracture, upper shelf energy, 30 ft-lb level nil-ductility transition (NDT) l temperature, 50 ft-lb level NOT temperature, and photographs (at least IX) of each pair of fracture surfaces. The Charpy impact data was prepared and reported in accordance with ASTM E185-82.(8) m arr a nc a - c o cu m nu s j
t
A -'4 -a m,-a, __-- -
. i 26 5.3 Tensile Properties Tensile tests were conducted using a screw-driven Instron machine having a 20,000 pound capacity. The tensile properties of base metal, weld metal, and HAZ metal specimens were determined following the procedures of ASTM E8-81,(24) " Tension Testing of Metallic Materials", ASTM A370-77,(ll)
" Mechanical Testing of Steel Products", and ASTM E21-79,(25) " Elevated Temperature Tension Tests of Metallic Materials". The samples of each material were tested at room temperature (~68 F), 200 F and 550 F. The representative operating temperature of the^Monticello Nuclear Generating
- Plant was 550 F. Temperatures of the specimens tested at elevated temperatures were monitored by two Chromel-Alumel thermocouples attached directly to the gage length. As required by ASTM, temperature control was maintained to + 5 F of the desired test temperature for 20 minutes prior to start of, as well as during, the tensile test. Tensile specimens were heated by mean's of a hot air-furnace.
- The testing machine crosshead speed was 0.005 in./ min from the beginning of the test until well past the 0.2 percent off set yield point.
The crosshead speed was then increased to 0.05 in./ min and held at this speed to the end of the test. A knife edge extensometer was attached directly to the tensile specimen central one inch gage section. A strain gage unit sensed the differential movement between the two extensometer extension arms which were attached to the specimen gage section by two vee notched knife edge bars.
The extension arms are required so that the strain gage can be located outside the furnace hot zone during elevated temperature testing. Elongation of the tensile specimen (at a crosshead speed of 0.005 in./ min) was measured to a point beyond the yield point using the strain gage extensometer over a one inch gage section. Once the yield point was passed, the crosshead speed was increased to 0.05 in./ min and the specimen elongation determined by multiplying the crosshead speed by the elapse time and dividing by the
- specimen gage section length (1.0 in.). After testing, each broken tensile specimen was reassembled using a special jig, photographed, and the distance
- between the punch marks measured. .Each specimen was also photographed end-on to st.ow the fracture surface.
marv a t o s - c o cu m n u s
27 Load-elongation data were recorded on the testing machine strip chart. 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. Total i
elongation was also determined from the increase in distance between two punch i
marks which were made in the gage section prior to testing.
The Instron load cell was calibrated prior to testing using a strain gage tensile bar which had been calibrated against N85 traceable standards.
The Instron crosshead speeds were also determined using a calibrated stop watch and a calibrated dial indicator. The extensometer was also calibrated before tensile testing using an Instron high-magnification drum-type extenso-meter calibrator. The calibrator was calibrated using N8S traceable standards.
5.4 Chemical Analysis The method of X-ray fluorescence (XRF) was used to determine copper (Cu), phosphorus (P), nickel (Ni), molybdenum (Mo), chromium (Cr), manganese (Mn), vanadium (V), silicon (Si),andsulfur(S). Each sample consisted of a l separate half of a broken w31d metal Charpy specimen which was polished through 600 grit grinding paper to provide a satisfactory surface for analysis. Both tantalum and aluminum masks were used to accommodate the sample. The masked-down samples and N85 standards (with known amounts of each element) were bombarded with primary X-rays to produce measurable character-istic or secondary X-rays of the desired elements. These characteristic or j secondary X-rays which result from inner orbital electron jumps of a i particular element are produced in proportion to the amount of that element in
[ the sample. Qualification and calibration was achieved by comparing the
, ' accumulated intensities and wavelengths of the X-rays from the sample to those from N85 standards possessing a known concentration range for each P
element.
sarv a L Ls - c o Lu m m u s 1
1
-..-?.-,A----..-_.. _-
28 The procedure for the chemical analysis for the elements listed above involved counting on the major linas and at off-line background positions. Counts were accummulated for up to 200 seconds at least twice for each sample to improve counting statistics. Electronic pulse height analysis (PHA) which allows elimination of excessive background due to the radioactivity of the sample was incorporated for the phosphorous, vanadium, silicon, and sulfur analysis. This PHA provided greater sensitivity in the net intensities for elements of low concentration.
The standards used for this analysis are certified NBS standards.
They included low alloy steels standards Numbers 1161 through 1169, and cast steel standards Numbers 1104 through 1183.
The XRF procedures used in this program are those in general use throughout the industry and are described in the literature. Two sources that g
l typify common practice are:
(1) Theory and Practice of X-Ray Fluorescence; Philips Electronic
, Inst., Mt. Vernon, New York.
! (2) Principles and Practices of X-Ray Spectrochemical Analysis; E.
P. Bertin; Plenum Press (1969).
In addition to the nine elements listed above, Charpy weld metal specimens were drilled and the chips (between 1 and 2 g) were sent to the Westinghouse Analytical Laboratcry at Waltz Mill, Pennsylvania, for carbon (C) analysis. Each sample was analyzed for its carbon content using the combus-tion gravimetric method according the ASTM E350-82(26) Sections 169 to 174.
A second method was used to chemically analyze the unirradiated archive samples for Cu, Ni, Mo, Cr, Mn, V, Si, S, and C. These elements were t
analyzed by inductively coupled argon plasma (ICAP) where the selected wavelength for the analyzed elements were computer controlled and the data was compiled using a software system for the required operating functions and computations. Interelement and interference corrections were provided by the calculational system. Standards used for this analysis method were certified NBS standards and included low alloy steel standards Numbers 1161 through i 1169, and cast steel standards Numbers 1104 through 1183. The phosphorus content was determined using the wet chemistry molybdenum blue-photometric method according to ASTM E350.
BATTELLE -COLUMBUS
o . . ,
I i
l 29 6.0 RESULTS AND DISCUSSION 6.1 Neutron Dosimetry f
Introduction The neutron environment to which a surveillance capsule has been exposed must be known so that the pressurt vessel material property changes (tensile and Charpy V-notch pr. wrty changes) can be related to that environ- I ment. However, the exact neut.:,n spectrum is very complicated and varies over i the operating history of the reactor. Therefore, the Monticello surveillance program utilizes iron and copper dosimeter wires to yield an integrated flux at the capsule position. The activation process is both time and energy dependent and a computer code is used to establish the neutron energy spectrum at the capsule position. Once the integrated flux at the capsule has been established, the flux or fluence >0.1 MeV and >1.0 MeV can be calculated at
_ positions within the pressure vessel wall and at angular positions around the vessel.
Analytical Method The determination of the neutron flux at the capsule, and subse-quently in the pressure vessel wall, requires the completion of three procedures. First, the disintegration rate of the product isotope per unit mass of the flux monitor must be determined. This has been discussed earlier under experimental procedures. Second, in order to find a spectrum-averaged' neutron cross section at the capsule location, the neutron energy spectrum i must be calculated. Third, the neutron flux at the capsule must be found by calculations involving the counting rate data, the spectrum-averaged cross sections, and the operating history of the reactor.
m arv a t u s - c a tu m o u s
30 The energy and spatial distribution of neutron flux in the reactor were calculated using the DOT 3.5 computer program.(20) 00T solves the Boltzman transport equation in two-dimensional geometry using the method of discrete ordinates. 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 arbi-trary order.
The two-dimensional geometry that was used to model the Monticello reactor is shown in Figure 8. As seen, there are 17 circumferential meshes and 51 radial meshes. Capsule 1 includes circumferential meshes 7 and 8 and radial meshes 41, 42, and 43. Third order scattering was used (P3) and 48 angular directions of neutron travel (24 positive and 24 negative) were used (58 quadrature). Neutron energies were divided into 22 groups with energies from 14.9 MeV to 0.01 eV. The 22 group structure is that of the RSIC Data Library DLC/ CASK (21), and neutron absorption, scatt. ring, and fission cross sActions used are those supplied by this library. The core shroud, jet pumps, and liner are Type 304 stainless steel. The capsule is also modeled as a solid piece of 304 stainless steel. The reactor pressure vessel wall is SA5338 steel. The reactor core was mocked up as homogenized fue'l and water having the densities found in the operating reactor. The water in the core region has a density consistent with the average coolant temperature in the core (550 F) at the operating pressure of 1015 psia. Finally, the fuel was a source of neutrons having a U-235 fission energy spectrum. The relative power in the assemblies nearut the capsule, during the interval the capsule was in j the reactor, is shown in Figure 8.(27) A plane view of the Monticello reactor physical geometry at the core midplane is shown in Figure 8 and because of.
symmetry includes only a 1/8th segment.
The neutron spectrum at the capsule center, 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.l.0 MeV. As can be
(
seen, the capsule spectrum is considembly harder than the fission spectrum.
L This is caused by neutron travel throv3n water.
BATTELLE -COLUMEUS
I B 31 280 17 76 273.35 - 9 M #
262.18- - -
c N ~
' -d$$? c',73 ,, 12 i ry
. 10 240 -
, e, Total = 51 Meshes t S 4/ #
220 -
212.41 207.98 qw 200 - u.~ .
/i , ,
0.4ssa 0.4415 0.371s %#;
180 -
0.8301 0.7957 0.5407 I
1% =1.0186 = - , .,
- 1. cote
'o.s241 0.es30 0. sos 2 0.5031 0.37ss
- d. 159.96 -
1osat 1.1425 1.0527 1.03s4 % oJs27 c.8521 g d
l '
No.ess2 a.4aos
- 1.s313 N 03:14
[ k g
l no -
1.0313 1.0152 0 ,ses 100 -
80 -
60 -
Numbers in Box Represents the Relative Power in Core i
20 :
'. il 0 I I I I l I I I I I O 20 40 60 80 100 120 140 160 180 200
- Destance From Core Center (cm)
FIGURE 8. MONTICELLO CORE, INTERNAL VESSEL STRUCTURES, AND VESSEL WALL GE0 METRY USED IN THE DOT CALCULATION m art s c t s - c o tu m m u s
32
=
=
m s,.an
___u si an 1.0 _ at Capsule
= ,
=
i' l
10-1 y l_ _
_= ,
{s, i ,-2 _
=
-s__,
1 -
= i_ _ _ _ _,
i i
u _ _ _ _, ,
, .- l t 10-3 _
l j 5 i_____,
_ u
_ l i
,g i._______
=
=
irs _
_=
,, I I I I I I I I I I I I I I O 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Neutron Enerw (MeV) s b FIGURE 9. COMPARISON OF DOT SPECTRUM WITH FISSION SPECTR'JM AT THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE m ar r a s. i. s - c a s. u swi n u s
- - - - - - g. ,v- - . . -
,--c..,, , - - - ~ , - , , . - - - - - - - , - - - - , - , , . . .
i 4
33 Based upon the fluxes calculated by DOT at r mesh 42 and 6 mesh 7 and 8 (the two radial centered meshes used to represent the capsule and the region in which the flux monitors were placed), effective cross sections )
'R (E > 0.1 MeV) and 'R (E > 1.0 MeV) defined as: l l
- R (E > Ec) =
[a(E)+(E)dE
'(Ec) $ (E)dE were calculated for ' iron and coppe" in each of the two meshes. The results are shown in Table 3 for aR (E > 1.0 MeV) which is of most interest.
Using the results of Table 3 and the geometry shown in Figure 8, the cross _section appropriate to each of the monitors can be interpolated. These values and other nuclear constants needed in the third step of the flux-finding procedure are given in Table 4.
In the third step, the full power flux at the capsule location is determined from the radioactivity induced in the monitor foils, the effective cross sections calculated for the monitor elements, and the power history of the reactor during capsule exposure. The fluence at the capsule is then cal-
- culated from the integrated power output of the reactor during the exposure interval using the equations outlined in the Experimental Procedures Section of this report.
$(E > Ec)= A/N a(E > Ec) C
- . This equation was used to find fluxes based on the surveillance capsule acti-
- vations. The time intervals were taken as one month each and a time inte-l grated relative power value for each month and for each fuel assembly was used
[ for the fractional power level values.
Calculations of the flux and fluence were made with the DECAY code.
The reactor power history was supplied in a private communication.(33) t 1
m ary m o u s - c o cu m n u s
34 TABLE 3. CROSS-SECTIONS FOR THE IRRADIATED FLUX MONITORS (E>1MeV) IN RADIALLY CENTERED TWO CAPSULE MESHES (MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE)
Material . Energy Cross-Section (Barns)
Cu 0.1 MeV 1.7558 x 10-3 1.0 MeV 3.0214 x 10-3 Fe 0.1 MeV 1.08% x 10-1 1.0 MeV 1.8749 x 10-1
/
TABLE 4. CONSTANTS USED IN 00SIMETRY CALCULATIONS FOR THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE Cross-Section, Isotopic Threshold Barns
. Target, Abundance, Energy, Product (E>1.0 MeV)
! Reaction percent percent MeV Half-Life (E>0.1MeV) 54Fe(n.p)S4Mn 99.865 Fe 5.82 1.5 312.6 days 1.8749 x 10-1
, 1.0896 x 10-1 1
63Cu(na)60Co 99.999 Cu 69.17 5.0 5.27 years 3.0214 x 10-3 1.7558 x 10-3 ,
I-a j
marre tt a - c o cu m n u s 1
. . . - ~ -. - .-.
e-.-. e ,,- - - - - - - ,g-p.-,,.w w -m,w- ,--w v---
35 -
Dosimetry Results The Monticello Nuclear Generating Plant surveillance capsule baskets both had the binary code number 19 which corresponds to that number assigned
, to the Northern States Power Company Monticello Reactor.(7) Both baskets had the capsule number 1. The surveillance capsule was located at the 30 degree azimuthal position at approximately the core midplane position and about i
9/16 in, from the inner pressure vessel wall. This capsule was in the reactor for 2786 equivalent full power days or about 7.63 equivalent full power years.
The Monticello Nuclear Generating Plant design thermal output is 1670 Wt -
Four iron (Fe) and four copper (Cu) neutron monitor wires from
, Charpy packets G-2, G-6, G-7, and G-8 were counted to determine their specific activity. The reconnended ASTM procedures (28-32) were followed in determining the specific activity of the Fe and Cu wires. Each dosimeter monitor con-sisted of an approximately 4-inch length of wire which was rolled into a small coil for counting. The count rate was determined for each wire. The fast flux and fluence calculated using the count rate therefore represented an average over the 4-inch length of that wire. The > 0.1 MeV and >1.0 MeV full power flux and fluence calculated from initial startup to November 1981 are given in Table 5 for each of the dosimeter wires along with the average of the flux and fluence derived from the Fe, Cu, and Fe plus Cu.
Using the average fluxes (average of Fe and Cu) of 2.037 x 109 n/cm2/sec for E > 0.1 MeV and 1.215 x 109 n/cm2/sec for E > 1.0 MeV, the fluxes at full power at the-inside of the pressure vessel wall, at lit T and at 3/4 T directly behind the capsule (30 degree position) and at the maximum position (*3 degree position) were calculated. The flux results are tabulated in Table 6. The end of life (EOL) fluences were also calculated and tabulated in Table 6 assuming a reactor pressure vessel lifetime of 40 years and operated at 80 percent full power. The fine mesh and time integrated relative power values (33) shown in Figure 8 for each fuel assembly was used in
, the DOT 3.5 code to generate the values in Table 6. A plot of neutron flux (E > 1.0 MeV) as a function of azimuthal angle (in degrees) is shown in Figure 10. The fluence values at the maximum position for inner vessel wall, m a r v a t i. e - c o c u m m u s
-= ,r ---------,4,e_m--- .,_ _ . . , ,m,. ..-- - , -_ , - - - , -
,,- e
36 TABLE 5. FLUX AND FLUENCE VALUES AT THE MONTICELLO SURVEILLANCE CAPSULE (30 DEGREE AZIMUTHAL LOCATION)
Dosimeter Full Power Flux Fluence
- Energy Material (n/cm2/sec) x 109 (n/cm2) x 1017
> 0.1 MeV Fe(G-6) 2.066 4.973 (G-7) 1.995 4.801 (ti-8) 2.157 5.192 (G-2) 1.847 4.446 Average of Fe 2.016 1 0.131 4.853 1 0.315 l
Cu(G-6) 2.163 5.207 (G-7) 2.131 5.130 (G-8) 2.309 5.558 (G-2) 2.030 4.886 Average of Cu 2.158 + 0.115 5.195 + 0.'278 Average of Fe 2.087 1 0.137 5.019 1 0.0332 and Cu
> 1.0 MeV Fe G-6) 1.203 2.895 G-7) 1.161 2.795 G-8) 1.256 3.023 I (G-2) 1.075 2.589 Average of Fe 1.174 + 0.076 2.826 + 0.183 Cu(G-6) 1.260 3.032 (G-7) 1.241 2.987 (G-8) 1.344 3.235 (G-2) 1.182 2.845 Average of Cu 1.257 + 0.067 3.025 + 0.161 Average of Fe 1.215 1 0.080 2.925 1 0.192 and Cu
- Fluence based on 2786 equivalent full power days.
m ar r a i. L a - c o c u m n u s
, . . . . . . . . . . _ _ - _ _ _ _ _ _ _ _ _ _ _ ____ _. . _ _ ~
1 s
(
TABLE 6. FLUX AND FLUENCE BEHING THE MONTICELLO SURVEILLANCE CAPSULE AND AT THE MAXIMUM VESSEL WALL POSITION I
U Fluence in Vessel l 4 Full Power Flux in Vessel. Behind Capsule (300) Maximum (30) i Energy Location Behind Capsule Maximum Nov. 81 (1) EOL (2) Nov. 81 (1) Ed.(2)
Y (MeV) (x109n/cm2/sec) (x109n/cm2sec).
/ (x1017n/cm2) (x1018 n/cm2) (x1017n/cm2) (x1018n/cm2) e n (300) (30) i I
( n > 0.1 Surface 1.897 6.995 4.567 1.915 16.837 7.059 ,
! > 0.1 1/4 T 1.703 6.430 4.099 1.719 15.477 6.488 h > 0.1 3/4 T 0.865 3.261 2.083 0.873 7.849 3.290 0 > 1.0 Surface 0.979 3.910 2.356 0.988 9.412 3.946 o > 1.0 1/4 T 0.735 2.990 1.769 0.742 7.197 3.018
> 1.0 3/4 T 0.297 1.187 0.714 0.300 2.858 1.198 (1) Fluence based on 7.63 equivalent full power years.
(2) Fluence based on 32 equivalent full power years.
a b
E I I
l l-38 ,
4
[ 1010
~
h
= a g g _
s -l. m.
y At Full Power
. j Surfeos as g; 108 7
e-1 m
~
.h 2 -
3/4 T F -
?
e I
k-" 10s l I I I "
0 10 20 30 40 50 Arirauthal Angle (des) 5 FIGURE 10. CALCULATED FLUX (E > 1 MeV) AT THE MONTICELLO 30 DEGREE CAPSULE INNER WALL, 1/4 THICKNESS, AND 3/4 THICKNESS ,-
AS A FUNCTION OF AZIMUTHAL ANGLE marr e c t s - c o tu m m u s =
39 1/4 T and 3/4 T are plotted as a function of time in equivalent full power years (EFPY) for the Monticello vessel in Figure 11. The lead factor, i.e.,
the ratio of the flux (E > 1.0 MeV) at the surveillance capsule to the largest flux (E > 1.0 MeV) received by the vessel wall at any azimuthal location, is approximately 0.31 (1.215 x 109/3.910 x 10 9 ) at the vessel surface. This result indicates that the flux at the capsule actually lags the flux at certain vessel wall positions. The lead factor at the pressure vessel 1/4 T position was calculated to be 0.41 (1.215 x 109/2.990 x 109) and 9
1.02 (1.215 x 109 /1,187 x 10 ) for the 3/4 T position. ,
The surveillance capsule end of life (EOL) fluence values' (2 > 1.0 MeV) predicted (34) by the General Electric Company (GE) at the 1/4 T is 1.2 x 1018 n/cm2 which is higher than the BCL calculated value of 0.74 x 10 18 n/cm2 (see Table 6). In o. der to correct for azimuthal variations, GE applied a factor of 1.4 to their calculation and obtained a maximum pressure vessel E0L fluence (E > 1.0 MeV)ut the 1/4 T position of 1.68 x 1018 n/cm2 while BCL calculgted 3.02 x 1018 n/cm2 The GE values have an expected accuracy of 1 30 percent whereas the BCL values have an expected accuracy of 120 percent.
Therefore, the upper bound of the maximum pressure vessel EOL f1- 1ce value (E >'1.0! AeV) at the 1/4 T position predicted by GE is 2.2 x 1( " .1/cm2
~
(1.2 x 1018 n/cm2 x 1.4 x 1.3) and as calculated by BCL, is 3.6 1018 n/cm2 s (3.02 x 1018'n/cm2 x 1.2). Therefore, since the BCL calculated fluences were ~
dsrived using the most recent dosimetry data, sthe power history of the Monticello reactor, and the two dimensional 00T 3.5 and DECAY computer codes, ;
it is concluded that an azimuthal correction factor much larger ,than 1.4 is required for the Monticello reactor pressure vessel.
When comparing the BCL end of life 1/4 T fluence values for >1.0 MeV I
energy range directly behind the surveillance capsule (at 30 degrees lazimu . s thal) and the maximum position fluence value (at between 0 and 5 degrees azimuthal) the azimuthal correction factor is more on the order of 4.0 (see values in Table 6). It is believed that this very high azimuthal correction factor is a result of the small inside diameter of the pressure vessel (about
. .206.7 in. ID) and the closeness and the relative high power level in the fuel assemblies at the O to 15 degrees azimuthal position.
1 m arv a t u s - c o tu m o u s r
4 %
40 1019, ps
_ sist 101 s _
~
gle
- I _
o x -
s N-
.1 8
4 1017 i
1018 ; l l l l l l 0 5 10 15 20 3 30 35 Time (fun Po s Years) t .
FIGURE 11. FLUENCE AT 14 T AND 3/4 T POSITIONS AS A FUNCTION OF TIME
-, FOR THE MONTICELLO NUCLEAR GENERATING REACTOR VESSEL i
1; .
i.
m ar y a t. i. e - e o i. u u m u s i
t a 41 I
6.2 Charpy Impact Properties 6
Introduction A reactor pressure vessel receives a significant fast neutron i exposure during operation and is therefore subject to radiation-induced ,
embrittlement. Charpy V-notch specimens were fabricated and irradiated in a l Monticello surveillance capsule at'the 30 degree azimuthal position and c 0.56 inch from the vessel wall. The specimens were then removed and tested.
! Appendix G of the ASME Boiler and Pressure Vessel Code,Section III, I l
Division 1 (Nuclear Power Plant Components) presents a procedure for taining allowable loading for ferritic pressure retaining materials to prote.. . against nonductile failure. The procedure is based on the principles of linear elastic fracture mechanics. 1 i .
Analytical Method l
Charpy V-notch. tests were conducted over a range of temperatures.
The impact energy, lateral expansion, and fracture appearance for the irradiated specimens were determined from the tests.(22) Plots of impact property versus test temperature were plotted for each type of specimen (base
! metal, weld metal, and HAZ metal) using the hyperbolic tangent fit. From l
these data, the temperatures.at which 30 ft-1b, 50 ft-lb, and 35 mil lateral l
expansion occurred were determined and the upper shelf energy for each type of
! specimen was also determined.
i i
i l
.....u.- m o-.o.
1 1
a .
i
- 42 l Charpy Impact Test Results l
j Twelve irradiated base metal Charpy V-notch impact specimens, l l thirteen irradiated weld metal Charpy V-notch impact specimens, and thirteen ;
irradiated HAZ metal Charpy V-notch specimens were tested. The results of tests conducted between 0 and 400 F for the base metal specimens are listed in Table 7. The results of tests conducted between -80 and 225 F for the weld metal specimens are listed in Table,8 and the results of tests conducted between -79 and 300 F for the HAZ metal specimens are listed in Table 9. In addition to the total impact energy values, the measured lateral expansion values and the estimated fracture appearance for each specimen are also listed in Tables 7, 8, and 9. The total impact energy is the amount of energy absorbed by the specimen tested at the indicated temperature. Lateral expan-sion is a measure of the plastic " shear lip" deformation produced by the
~
striking edge of the impact machine hammer when it impacts the specimen.
Lateral' expansion is determined by the change of specimen thickness directly adjacent to the notch location. Fracture appearance is a visual estimate of the amount of shear (ductile type of fracture) appearing on the specimen fracture surface. Additional data, along with a discussion of test results and of the procedures for conducting instrumented Charpy V-notch impact
- .- testing, is given in Appendix A.
Plots of the impact properties (impact energy, lateral expansion, and fracture appearance) versus test temperature are graphically illustrated in Figures 12 through 20. These figures show the change in impact properties as a function of temperature. Note that two weld specimens with a FA8 Code designation beginning with D were tested along with the set with the designation beginning with J. The HAZ specimen 072 was not plotted in Figures 18, 19,-and 20 because the fracture occurred in the base metal (See noteunderTable9). Figures 21, 22, and 23 show the fracture surfaces of the Charpy specimens.. A summary of the Monticello surveillance capsule 1 Charpy
- i. V-notch impact test data (including the 30 and 50 ft-lb transition temperatures, the 35 mil lateral ~ expansion temperature,-and the upper shelf energy)'is given in Table 10. The upper shelf'is relatively constant at*
- Text continued on page 59.
m ar r a L L s - c a s. u m m u s
l 43 TABLE 7. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE l
, Specimen Test Impact Lateral Fracture l Identification Temperature, Energy, Expansion, Appearance.
F ft-lb mils Percent Shear JE3 0 7.0 11.6 10 JOU 40 24.8 22.6 25 JDJ 60 30.5 30.0 25 JE1 76 44.1 35.8 30 JDY 100 55.4 43.6 35 J01 110. 58.7 45.8 40
'JES 120 43.3 40.6 40 JCP 160 75.5 57.6 55 JE4 200 91.0 74.4 - 100 JDA 300 110.0 69.8 100 JOS 350 103.0 73.8 100 JD4 400 105.0 71.2 100 1 ._ .
l (a) Instrumented results are contained in Appendix A, Table A-1.
i sav r e t t s - c o Lu m m u s
a .
44 TABLE 8. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE Specimen Test Impact Lateral Fracture Identification Temperature, Energy, Expansion, Appearance, F ft-lb mils Percent Shear JEX -80 24.5 20.9 25
-60
,JEL - 22.5 20.6 20 JJE -40 68.7 54.0 40 JJP -35 22.0 24.6 30 068 -30 22.9 32.0 . 30 JEM -20 39.5 34.4 35 D57 -15 78.5 70.2 65 JJM 0 36.3 30.8 35 JEP 0 -65.2 51.2 55 JEY 20 75.8 58.8 50 JJT 76 96.0 81.4 90 JJ7 160 118.S 90.2' 100 JEU 225 127.8 86.8 100
! (a) Instrumented results are contained in Appendix A, Table A-2.
i n a r r e i. c a - c o L u na m u s
45 TABLE 9. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED l HAZ METAL SPECIMENS FROM THE MONTICELLO i 30 DEGREE SURVEILLANCE CAPSULE I
Specimen Test Impact Lateral Fracture Identification Temperature, Energy, Expansion, Appearance, F ft-lb mils Percent Shear i
JKD -79 19.5 32.6 15 JLE -60 28.5 25.4 20 JKK 65.0 49.4 35 l dKA -30 71.3 54.0 50 l JLC -20 40.0 33.6 50 JKT -10 33.0 27.6 40 JL8 -10 50.1 38.6 50 JL2 0 57.9 43.0 50 l JKM 76 110.2 84.4 100 JLM 159 103.0 78.0 100 JLK 225 123.3 94.8 100 JK5 300 113.0 82.0 100 l
072*- 40 21.3 23.0 (a) Instrumented results are contained in Appendix Table %, Table A-3.
- The notch was located approximately 1/8 inches from ti.e fusion line as l determined by posttest etching. ASTM E185 specifies the notch to be less than l 1/32 inches frcm the fusion line. Therefore, these tett results were not l plotted in Figures 18, 19, and 20.
i l
1 l
l m arr a c6 s - c o tu m m u s l
. - _ . ._._____.____u. _ - _ . . _ . _ ,_ _ . . _ . -
e e ,
46 m
~ m
~ T C -
5e
'-i
$U p m wE a -
w WGw
> Ed
~ g--
a ms mw w Wd N o. wWU 3 W5
- IL
-a O
W Ew5 HW
& Qg-dhd
>-25 L "d l g b Q (J e _m m G w I
c i . . , _-
m S2I 001 S4 OS S2 0 8 1-1..f ADhl3N3 SATTELLE - C O LU M a y s
e a 47 m
- G T
5 El 5-!
tu m
"A k
e -
@ WI biw W*
E!
E-
- u. WE 5$
W a mes F
zmm CL g U -
5h Udu NE g5*W x
_.a G
m 5S"s H @6" Skd S it!!
Rwo g UHM
- G w
c I . I . f . I 3 GOI S4 OS S2 0 S1IH NOISNYdX3 lVB31V7 BATTELLE -COLUMaus
a i 48 g .
$d ne EI
- 5 mw cl -
l W" E!
=-
- G 55 u-Ns W Lt 3 sh t -
l E &v c
e-w med
'50 F
W 5-"
H W E =
- E ~ d
>. 35 9
aw 25 L3 W
\
U ~
\. W C'
G
' ' ' a BOI S4 BS EE B IN33W3d MV3HS SATTELLE - C O LU M S u s
49 G
S (D
6J ww HiS wn E
Eg W
. _ S N
ky m
rs t;;5 WE EG
' QM W Gw
. >=kb E E'"E o
& Mc w>
Sh
- w H IE W 65 Q.
K N_ J Jg;d N z edt' WWg as s ege ts!
O Bh 5
G G -
d g
w B c G
O e e s e e g est sat set s4 es sz e I
S87 .Lf Adhf 3N3 BATTELLE = C O LU M B U S
es*
J,
.I t
I m
S
.-e j.
, O m B l J an ~
l 0
$ B l
a z
B \
E u
Em
<m -
G I o n
W D J g 5 U O E , ,
x Wn -
o - ;
1 0
$ a ,
C 0
1 m , , . .
1
-100 0 100 200 300 TEST TEMPERATURE F 1
i FIGURE 16. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEWERATURE FOR THE IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE -
4 Il t l
51 a
M E
nd nu c.' EC W5 m
.m MM g-
!Cf E
[2 gg
- u. gg Di w w w 2 =f a!d p
MB i-. E m S <E wSw
~% SWW a s med
'EC
$ k~$
W sIa a-w
-W5 U t*E Es w a.R m B - m G g b
w G
B 5 s t O
O
, , , 3 OSI S4 BE S2 0' 1N3383d NY3HS m ar v e s. u s - c o c u m n u s
___.m_._.__.__. _ _ _ _ . _ _
m m
1-
.-e t
in N -
a
.-e f
(1 O
a O o
mN m
. 4 J 4 I o t r m -
b r
a >- a E G i o, m
n !f!
4 o w in e - g e
c E .
a l O G c n o N -
O
, i ,
m . - . ,
-100 g 100 200 302 TEST TEMPERATURE F
. FIGURE 18. CHARPY V-NOTCH IW ACT ErrRGY VERSUS TEST TEWERATURE FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE 4
l
.m - - m % ..m A1, 9
a 0
(1 0 $ -
3 5
E G a ER -
a m a
n w a o a E E D D a
! lN -
e g a -
100 0 ISO 200 300 TEST TEMPERATURE F FIGURE 19. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEWERATURE -
FOR THE IRRADIATED HAZ ETAL SPECIENS FROM lHE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE .
.L I
3 a e G !
H C n -
O n i i
0
> 10 4 b -
4 F .
o z ,
r W r U i E i A m m -
BB B m n '
I o $ 8 r w C I E
- nn o .
N -
C . '
i O 1
m __
i . . .
- -100 0 100 200 j
300 3
TEST TEMPERATURE F L t FIGURE 20. CHARPY V-NOTCH PERCENT DUCTILE SHEAR VERSUS TEST TEWERATURE 1
FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE ,
i l i JE3 JDU JDJ JE1 JDY JD1 l
i >
'i
\ %
',$h,j$~ .j! ' T.'"j. h.. i .).' ' R
.- I
- s % ,
.,,il.$ 1 f,: ' -(i.'*
]id,1 ' 2 r . ' " 1.T $
4 4
. h5 . Lt .
m r
r 2X a
i
- n JES JCP JE4 JDA JD5 JD4
?
c =
? -l.'.>
'l+1.,,Q:. ,
4 .'.? ? Y l W 7' Y it.:MC
~ : *; L ' . ..
. :; :.'.%l.E
. ; : '~-2.::l'%:'
"' r .: ; ']l t.L*...2. ::.
'.?' ' :l"#b l" l . *e .l.
.").5.'. .(*:s : -.+t -.
t 41 1 -
Ag
.{
mawA~ ,. .
e p.ip;t.,7l].j{
9- -
L gyg
- ..y g-g; , ;
t*kh:..:r,.. ... , 4 { ! I; i f.i, .[' ,x':* % . J ,Jd,; ci. @y i.1.T$ yt. y y:, .;M[A.; jr 1 ..
.a. h _ t.' -Y y ."x .: :..:
-+,: .e.:-:r C .:;; -l ?. :. N )Q;:
- p..' .j.%
- .;p? '* : . ,,..:. _ ; .; ;_ s.). ~r. : $:.. . .W'~TQ%;d 2X 1
i FIGURE 21. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR THE IRRADIATED i
BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE i l SURVEILLANCE CAPSULE .
?
4 i l
L ._ . _ , , -
N '
JEK JEL JJE JJP D6B JEM D57 t , i - r,
,,.s.. l*h ) ' -
.P *I 'A
' uk '.
s
,')l,
.Q ,r '
f.
- : s',
..g 3 -_ g
. !{f< *;.{'- *L-
.g - ..
x- m - ~
e...
'N b.
- T ;.,f, g ,h '
,k, -
" d, . "
6[j.'j ,' " l. .
- . $!j;.
o g . -
c E 2X G
l n E o JJM JEP JEY JJT JJ7 JEU
[ .; g.% ;; m.g g a:- . . . . gn . ._3.. . .;; ,
g;4 :f::cy)9 fy ;y. s., pg. . gns y;.5 ;:-;; . ..u';..3
. e. ..~,.f;;;; ~g .....
.,s.; ';m:;b._s.. ; ;.. : 4 . . . . :.
o h.!? I kdl .;g ;h,.' .;[.( N.. q [:Nk. .
k g, Ab, gg y- M ,pN 4 %.r
+ .
~?f;;ff .[. ?. l l, ' ; i. ' J, , .m .1 q*~t R ~ ^ bi , y
'lr gig.&. . l~;f t;;e:yf . ...{ _; l,:
. ' . , [ l~1.;
5.];\
. t \ I ,.
o .;3 1. ..v'.,..+H:
-- -- - e 2 3,-
- :,,ga e. .. <
g-R O'? 151,Mf ;.--p.y ..; . . .l4( $.._,
l g .. ._h f {,f:4 y ' 'w .L:; -.- ' A.
_l ,. .
. ^ lp 7 ' ~~_
. :, (_ ,
- _ ' . l ' ,,l?_
- '~ ~':
2X FIGURE 22. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR THE IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE I
JKD JLE JM JKA JLC JKT JLB
'.,_..,_:c.m-TQ 4?Wb.1%; ?.:':- l-1 z.q 9
+0h*.MttQ.l~Zf%
- A !Q f.- l ':',2 ' Q! ' :g*f -::..~ .:y ;,. ::7..
.ph. + < ,^;j.6
.x- 4;X?,. .. -: .. ~y . ;~. y
. + - : .. t ~~
- . , , . - _g ,. q i .
f i :; ..i. R ' n .., .~;d.s T. :.
+ . . ' ; :-s 3;y...- :.Q:3 1 : .a1.hy:
,, 9.:b;., S c:m .; * :ya.t.:: ,. , _ . 3 ; ; ; __. ; ,x p-(
[a 2X 0
0 JL2 JKM JLH JLK JK5 D72 e
r
. ' =-; ; e .:y: W. ::- .' ., --,, ,a :, , :.. *- .T : . ,;v :-..i..'. .r~. .
c y ,. .#$v.N% .
w v;; c..
. , . . . . 3. ' .-. ' >.,
.- > , . . .1 dqqwy' ~ ; . . :.e . . -
., .. . . , r-g n .
17 . + ,.y =;.c ns.s. - ...,%..
r.
s ',.,p..
t .
3 ,
~ " *
,{.- .. .. .!. . : ' y 4 j .
I ;,
.n. ~ .
a a a .n A_ a-b, "',yj.y y J .
- h. .
jj j'O g.py .,
?;
4
.S, G. , ..,, - . 4.: i ,i ?y -N '
j y*. ' ~ . . , .:
iY - . .. p ; ; yn . , - -
a m g%?=4 TOl d'4 % ' M q. . .
% i. Q-hkh.?:%I, 4,* .
.c y. -N%,,4 . ;m
- ._"$*' g'L.-:D,
! - . . ,- .; 3, y,: ' _ . . ,,_ y
(.. ,.
$. , . .] , 3 V,. . ,J. .T., __. .;.
2X FIGURE 23. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE
. CAPSULE EWM M ' EMEE' I
i .
4 0
TABLE 10. Su MARY OF CHARPY. IMPACT PROPERTIES FOR IRP.ADIATED MATERIALS
'4 FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE 4
, o r :
r i
o I
n E>1.0 MeV 30 ft-lb ~ 50 ft-lb 35-Mil Lateral Upper Shelf E
- o Fluence, Transition Transition Expansion Energy, j
[ Material n/c 2 Temperature F Temperature, F Temperature, F ft-lb Base 2.93 x 1017 56 100 85 109 2.93 x 10 17 o Weld -58 -15 -37 129
) HAZ 2.93 x 10 17 -67 -22 -45 118 1
t
59 109 ft-lb for the base metal,129 ft-lb for the weld metal, and 118 ft-lb for . . .
the HAZ metal. These valuse are well above this minimun allowable upper shelf d energy of 50 ft-lb specified in 10CFR50 Appendix G.
The unirradiated drop weight and Charpy V-notch impact data (16) are
) I shown below. =
Drop Weight Test TNOT Tenperature Charpy V-rotch Plate (F) (F) (ft-lb)
C2220-1 1-14) 0 10 60 C2220-1 1-14) 0 10 5- r C2220-1 1-14 C2220-2 1-15 0
0 10 10 81 81
'(
C2220-2 1-15 0 10 33 C2220-2 1-15) 0 10 61 The initial reference nil-ductility transition tenperatures (RTNOT) were established previously for the Monticella unirradiated base metal as 14 F and for the unirradiated weld metal at ?G F(16) The most recent NRC ruling (May 27, 1983) for Appendix G to 10CFR50, " Fracture Toughness Requirenents for Light-Water Nuclear Power Reactors," specifies that an adjusted RT NDT I#
irradiated spec. mens can be determined by adding to the intial RTNDT the enount of the temperature shift measured at the 30 ft-lb level in the average Charpy curve for the irradiated material relative to that of the unirradiated materi al . When such unirradiated Charpy curves are not available, the NRC g allows the use of Regulatory Guide 1.99 along with the chemical analysis for ;-
copper and phosphorus and fluence measurments to be used to calculate the shift in the reference tenperature (ARTNOT). The procedures outlined in g Regulatory Guide 1.99 were used to calculate the ART for both the j NDT t
Monticello base metal and weld metal. The calculated shifts were then added -.
to the initial reference temperatues for the base and weld metals to establish i an adjusted reference tenperature. This adjusted RTNDT can be used in y revising the plant pressure-tenperature operating curves. The copper content q for the base metal was 0.17 weight percent and 0.06 weight percent maximun for
}
g a
m o i
l 60 '
the weld metal. The phosphorus content for both the base and weld metal was 0.01 weight percent (See reference 16, page 4 and Section 6.4 of this report).
The maximum fluence (for neutrons with energies greater than 1 MeV) at the pressure vessel 1/4 T position was found to be 7.2 x 1017 n/cm2 at the time the capsule was removed (See Section 6.1, Table 6 of this report) and 9.1 x 1017 n/cm2 at the time of the extended outage which began on February 3,1984(9.65E7PY). Using these data and the procedures of Regulatory Guide 1.99, the adjusted RTNDT, (initial RTNOT + shift) for the Monticello base metal as of 2/3/84, was calculated to ba 56 F (14 F + 42 F) and 55 F (40 F + 15 F) for the weld metal. The weld metal was the limiting material at 7.63 EFPY because of the very conservative estimate for the weld metal initial RTNOT of 40 F. However, due to the high copper content of the '
beltline base metal, this material became the limiting material above a fast neutron fluence of 7.8 x 10 17 n/cm2 ,
The predicted peak end of life (EOL) shift assuming 32 equivalent full power years (EFPY) for the Monticello pressue vessel 1/4 T position was calculated to be 77 F for the base metal. For comparison to GE(16), an EOL shift assuming 40 EFPY for the 3 degree azimuthal and 1/4 T position was calculated to be 86 F for the base metal. This compares to a predicted shift of 155 F reported in reference 16 where the worst case (0.35 weight percent copper 1 was assumed for the weld metal at 40 EFPY. However, the NRC has since agreed (35) that this assumed copper content, which had been maximized because of insufficient data, need only be 0.10 weight precent maximum (the chemical analysis of the irradiated weld metal, which is listed in Table 12 of this report, fully supports this maximum 0.1 weight percent assumption).
Because of the lack of unirradiated (baseline) Charpy data, the shift in upper shelf energy can not be determined experimentally. However, using the procedures from Regulatory Guide 1.99, the predicted drop in upper shelf energy for the irradiated Monticello 30 degree surveillance capsule was found to be about 20 ft-lb for the base metal and about 15 ft-1b for the weld metal. The EOL drops were estimated to be at the most 30 ft-lb for the base t
metal and 23 ft-lb for the weld metal, The EOL upper shelf energies are, therefore, predicted not to drop below about 70 ft-lb. This is well above the minimum allowable EOL upper shelf energy of 50 ft-1b as specified in refer-
-ence 13. The results of the Charpy tests for all three irradiated materials BATTELLE -COLUMBUS
~~
- , o 61 l (base, weld, and HAZ) from the Monticello 30 degree surveillance capsule exhibited upper shelf energies greater than 100 ft-1b. Therefore, the unirradiated values certainly were above the minimum allowable unirradiated i upper shelf energy of 75 ft-lb as specified in reference 13 (10CRF50 Appendix G). i l
C.a Tensile Prt,perties '
f Introduction '
1 l
< l 1
The tensile specimens were irradiated in the~Monticello surveillance s capsule which was located at the 30 degree azimuthal position and 0.56 inch from the vessel wall. The tensile specimens were tested and the yield '
! strength, ultimate tensile strength, uniform elongation, total elongation, and reduction-in-area of the ir:adiated materials were determined.
Analytical Method
- Prior to testing, each tensile specimen diameter was measured using a blade micrometer and an initial cross-sectional ared was calculated for each specimen. Load-elongation data were recorded on a strip chart for each test.
The 0.2 percent offset yield load, maximum tensile load, uniform elongation, and total elongation data were taken directly from the strip chart. The per-cent elongation was calculated for a 1 inch gage secticn and was verified by posttest measurements of the increase in distance between the tensile specimen punch marks'(originally positioned 1 inch apart). The yield load and ultimate i load divided by the initial cross-sectional area provided the yield and ultimate tensile strengths, respectively. The percent reduction-in-area was calculated by subtracting the postto ' cross-sectional area from the initial cross-sectional area, dividing by the initial cross-sectional area, and l multiplying by 100. The fracture strength was calculated by dividing the 1 failure load by the pretest cross-sectionel area and the fracture stress was calculated by dividing the failure load by the posttest cross-sectional area.
m a r v a t i. e - c a s. u u n u s
i . .
i d
62 l Tensile Test Results l
The tensile test parameters and irradiated specimen tensile prop-erties are listed in Table 11 and plotted in Figures 24 and 25. This table lists the specimen number, materia!, and test temperature. Also listed are the 0.2 percent offset yield strength, ultimate tensile strength, fracture strength, fracture stress, reduction in area, uniform elongation, and total elongation for each specimen tested. Photographs of the tested tensile-specimen (longitudinal and end-on) are shown in Figures 26, 27, and 28. As
] can be seen, the necking occurred between the initial 1 inch punch marks for all nine tensile specimens and all failures were in a ductile cup-and-cone mode. A typical tensile test curve is shown in Figure 29.
Tensile tests were conducted at room temperature (75 F), 200 F, and 550 F. All three materials, base metal, weld metal, and HAZ metal exhnited decreases in yield strength, ultimate strength, and fracture strength when the test temperature was increased from room temperature to 200 F. These tensile properties appear, however, to recover partially for base and HAZ metal specimens, and the ultimate and fracture strengths appear to recover totally at the test temperature of 550 F when compared with the room temperature test results. The 0.2 percent offset yield strength and fracture stress exhibited a monotonic decrease with increasing test temperature between room temperature and 550 F for base and HAZ material types and between 75 F and 200 F for the weld material type. The percent reduction in area for the three materials was relatively constant at test temperatures of 75 F (room temperature) and 200 F but decreased slightly (about 6 percent) at a test temperature of 550 F. Weld specimen tension tests were conducted only at 75 F and 200 F. Within experimental standard deviation, the base metal and weld metal tensile elongations (uniform and total) generally decreased with increased test temperature. However, for the HAZ metal, both the uniform elongation and total elongation appear to decrease when the test temperature was increased i from 75 F to 200 F and appears to recover at the test temperature of 550 F.*
- Text continued on page 70.
s a v e s t o s - c o c u ns m u s
i TABLE 11. TENSILE PROPERTIES FOR THE IRRADIATED MATERIALS FROM THE MONTICELLO 30 DEGREE CAPSULE O Tesy Fracture Reduction
> Specimen Material Temp.LI) Strength, psi Stress in Area Elongation. percent (2) j No. Type (F) Yield Ultimate Fracture (psi) (percent) Uniform Total O
[0 JC1 Base RT 67,240 91,730 62,240 183,730 66.1 14.4 28.0(21.2)
JC2 Base 200 53,650 85,740 58,550 177,020 66.9 12.1 24.5(18.3) g J8M Base 550 58,300 87,650 64,780 160,000 59.5 12.6 22.1(17.3) o DC2 Base 550 62,630 90,120 63,140 162,300 61.1 9.6 19.6(14.6) c J82 Weld RT 71,590 85,340 50,920 192,310 73.5 13.9 27.4 l
[c J86 JC6 Weld Haz 200 RT 64,140 67,450 77,580 87,650 '
46,060 55,100 176,740 188,810 73.9 70.8 10.3 11.2 22.6 24.7 JCK Haz 200 64,080 82,140 51,020 181,160 71.8 8.5 20.8 JCM Haz 550 62,880 87,830 57,810 165,700 65.1 11.2 22.5 (1) RT is room temperature - 750F.
(2) The elongation is for a 1-inch gauge length and the values in parentheses are for a 2-inch gauge length.
S e
64 100 5 Ultimete strength Orrediated)
$ 0.2% Yield Strength Urredieted) oO - 3 a0 -
T 5
5 70 -
a0 -
O I I I I I 50 O 100 200 300 400 500 000 Test Temperature (F)
?
5 FIGURE 24. BASE METAL YIELD AND ULTIMATE TENSILE STRENGTHS VERSUS TEST TEMPERATURE FOR THE IRRADIATED TENSILE SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE m a r t s i. a. s - c a s. u m n u a l
- 1
65 100
& Reduction in Aree (irradiated)
E Total Elongation (Irradiated) 80 -
A A
= 80 -
N I
L 40 -
R : -
m g I ! I I I 0
O 100 200 300 400 500 000 Test Temperature (F) t FIGURE 25. BASE METAL TOTAL ELONGATION AND REDUCTION IN AREA VERSUS TEST TEMPERATURE FOR THE IRRAADIATED TENSILE SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE a a v v s i. t. m - e o a. u m a u e
L_7 - - - - -
^ ^ ~
- - - - . ._. . . - . - - . . . - . - __..: . . _ - .:- . ^ ~ ^ - - ^ ^ .
l .
i 1
66 3
l 2X JCl C-9894 & -9898 2X JC2 C-9887 & -9890 1 i
- 2X JBM C-9873 & -9888 1
4 2X DC2 C-9875 & -9889 ;
FIGURE 26. POSTTEST PHOTOGRAPHS OF THE IRRADIATED BASE METAL TENSILE
' SPECIMENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE -
SURFACES (MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE) !
i BATTELLE - COLUM5us
67 2X JB2 C-9895 & -9896 M+
f 2X JB6 C-9885 & -9891 l
I 1
- \
l i
4 FIGURE 27. POSTTEST PHOTOGRAPHS OF THE IRRADIATED WELD METAL TENSILE SPECIMENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE) ,
i I
m arv a LL s - c o Lu m e -3
)
1 68
, . . .w. . l 1
l l
i
! )
l
- 2X JC6 C-9893 & -9897 l
i
)
2X JCK C-9886 & -9892
] ,
i
~
.- ,. I
, .M -
2X JCM C-9874 & -9877 FIGURE 28. POSTTEST PHOTOGRAPHS OF THE IRRADIATED HAZ METAL TENSILE t SPECIMENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE) t e
I
.. .u.-coco..u. ]
l
69 4000 -
1 I m l D i
1
.a 8 00 *
, =
1000 -
O l l I I O 5 10 .15 20 W Elongotion (persont) 1 FIGURE 29. TYPICAL TENSILE LOAD-ELONGATION CURVE BATTELLE -COLUMBUS-
r 70 -
~6.4 Chemical Analysis Introduction It had been known for some time that the chemical composition of a pressure vessel steel affected the extent to which material properties such as fracture and crack propagation were changed during irradiation. The Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99 was issued as a guide for estimating the effect of copper and phosphorus on the reference nil-ductility (transition) temperature (RTNOT) as a function of fluence. In order to use this guide or to establish the copper and phosphorus content, a chemical analysis must be performed. It was originally believed that the weld metal was the or y Monticello core beltline surveillance material for which no adequate traceability could be found in existing chemical and physical '
properties reports.Id0) Therefore, base metal chemistry was not determined.
A chemical analysis was performed to establish the weld metal constituents including copper (Cu), phosphorus (P), nickel (Ni), molybdenum (Mo),
chromium (Cr), manganese (2), vanadium (V), silicon (51), sulfur (S),and carbon (C).
Analytical Method Each irradiated sample (one half of a broken weld metal Charpy V-notch specimen) was ground and polished through 600 grit grinding paper,
- masked-down, and bombarded with primary X-rays to produce measurable characteristic or secondary X-rays. Qualification and calibration was
- achieved by comparing the accumulated intensities and wavelengths of the secondary X-rays to those emitted by N85 standards. The standards possess a l known concentration range for each element. Counts on the major X-ray and at off-line background X-ray positions were accumulated for up to 200 seconds at least twice for each sagte to improve counting ::tatistics. Electronic pulse i
r s a v e s L L s - c o L u na s u s
.e. - - - , . _ _ , _ ,. _ , . - - _ .,m o, .,~_r_ ,.. - _ _ ___.__.._,,e.,-,_ ,-,_._,.,,,,.---._,_._~-._,_,.____.__.x_,.__,.,..--.,,.n _-..w-..._~_w,,,m
71 height analysis (PHA) was used for phosphorus, vanadium, silicon, and sulfur count evaluation to eliminate excessive background due to the radioactivity of the sample. The chemical analysis for Cu, Ni, Mo, Cr, and Mn content was 1 obtained using standard curves of characteristic X-ray intensities as a i function of the percent of each element in the N85 standards. The chemical analysis for P, V, Si, and S content was obtained by ratioing the net intensities of the characteristic X-rays for each element emitted by the weld metal sample to the net intensities obtained for each N85 standard. The N8S comparison standards were chosen so that the elemental composition (percent of each element) was as close as possible to the percent of each element expected in the Monticello Charpy V-notch weld metal samples.
Each irradiated weld metal Charpy V-notch specimen was drilled.
Chips from the weld metal drilling were analyzed for carbon content using the
, combustion gravimetric method outlined in ASTM E350-82 Sections 169 to 174.
, The unirradiated samples were analyzed for Cu, Ni, Mo, Cr, Mn, V, i Si, S, and C using the inductively coupled argon plasma (ICAP) technique and analyzed for P using the wet chemistry molybdenum blue-photometric method according to ASTM E350.
Chemical Analysis Results Three broken weld metal Charpy V-notch specimen halves were analyzed j for elemental constituents including Cu, P. Ni, Mo, Cr, Mn, V, Si, 5, and C.
The analytical results for the three irradiated weld metal samples are listed L in Table 12.
4 i
)t i
i savv a to s - c o cu m n u s l
. .- - -. . _ ~ _ _ _ _ _ . _ _ _ , . . _ _ _ _ _ _ _ _ _ _ _ _ , . . _ _ . - _ . . _ _ _ _ _ _ . . _ _ _ _ _ , _ _ , ~
l l
72 TABLE 12. CHEMICAL ANALYSIS RESULTS FOR IRRADIATED MONTICELLO WELD METAL SPECIMENS FROM THE SURVEILLANCE CAPSULE Elements. Weight Percent Specimen Cu P Mi Mo Cr Mn V 51 5 C JKA 0.06 0.01 0.92 0.46 0.05 1.04 0.010 0.20 0.01 0.077 JEL 0.03 0.01 0.95 0.51 0.03 .0.97 0.010 0.32 0.01 0.067 JEP 0.04 0.01 0.90 0.44 0.04 1.02 0.010 0.10 0.01 0.068 Calculated Accuracy 1% 15.0 --- 6.0 6.0 ---
2.0 --- 4.5 ---
5.0 Estimated Detection Limit, wt. 5 0.02 0.01 0.01 0.02 0.01 0.02 0.01 0.02 0.01 0.005 It can be seen from Table 12 that the irradiated weld metal elements (Cu, P, and N1) which have been identified as the major contributors to irradiated pressure vessel steel embrittlement are less than 0.1 weight per-cent for Cu, 0.01 weight percent or less for P, and 0.92 1 0.02 weight percent for N1. This copper content is consistent with that assumed by the Nuclear Regulatory Commission for the Monticello manual shielded-metal-arc-welded reactorpressurevesselshell.(35)
An archive section of the Monticello core beltline plate was obtained from the General Electric Company (GE). The section was cut at GE using a band saw and measured 5-1/2 x 5-3/8 x 5-3/8 inches. This section was stamped with the identification marks C 2220-2, STP-1, and an arrow indicating the rolling direction. This section was then sent to the Battelle Columbus Laboratories (BCL) along with the GE Inspection Report 5318 and a photograph showing the archive plate prior to removing the section sent to BCL. This photograph showed the stamped identification markings T5624, 1 - 15, C 2220-2, GE BASE METAL, STP-1, MONTICELLO,'and an arrow indicating the rolling m a r r a i. c n - c o c u m a u s
4
- 73 i
direction. These markings agree with those of the Monticello Piece Number 1-15, Heat Number C 2220, and Slab Number 2 described as one of the base metal
{._ plates in the GE Report NEDO 24194 "Monticello Nuclear Generating Plant Information on Reactor Vessel Material Surveillance Program" of October 1979.
- In this report, a reference is also made to the removal of the surveillance specimens prefixed with the letter D from plate STP-1 (NED0 24194, Appendix A, pages 60 through 68). However, no documentation could be found for fabri- ;
cation of the surveillance specimens prefixed with the letter J although it was the general consensus at GE that the J specimens were fabricated from i plate number 1 - 15.
To verify that the surveillance specimens prefixed with the letter J l were fabricated from the beltline plate 1 - 15 (C 2220-2, STP-1), an !
!- unirradiated archive tensile sample J8L for the Monticello pressure vessel program was obtained from the Northern States Power Company for chemical
, analysis. A sample was cut from the archive section described in the previous i paragraph for a similar chemical analysis. The sample from the section C 2220-2 (STP-1) was removed using a band saw and the sample was taken from
+
the 1/4 thickness (1/4 T) position along the rolling direction. This cut
! position and direction was used because the original sur've111ance tensile specimens were originally removed in this manner as described in NED0 24194.
Both samples were analyzed at BCL for Cu, P. Ni, Mo, Cr, Mn, V, Si, S, and C and the results are tabulated in Table 13.
, A comparison between these chemical results for the archive plate .
1 (C 2220-2) and the archive tensile specimen (J8L) indicates that the Cu, Cr, Mn, and S contents are identical, the Ni, Mo, and C agree within about one percent, the Si agrees within three percent, and the V agrees within about 13 percent. The P content was 0.005 1 0.001 weight percent for plate C 2220-2
, and 0.009 1 0.002 weight percent for the tensile specimen J8L. However, if the results are rounded to only two significant figures, both yield 0.01 weight percent P.
A comparison between the chemical analysis results reported in Y NEDO 24194 for plate C 2220-2 (listed as 1 - 15 in Table 13) and the results !
obtained at 8CL for plate C 2220-2, indicates (after rounding to comparable
- significant figures) that the Cu and P results are identical, the Ma agrees
! saves to n - c o Lu m ou s
n
. ,L. .
74 TA8LE 13. CHEMICAL ANALYSIS RESULTS FOR UNIRRADIATED MONTICELLO BASE ETAL BELTLINE PLATE :
Elements. Weight Percent Specimen No. Cu P Mi Mo Cr Mn V Si 5 C 1-15(a) 0.17 0.010 0.58 0.45 - 1.31 - 0.22 0.014 0.20 C2220-2(b) 0.166 0.005 0.659 0.431 0.096 1.41 0.014 0.315 0.010 0.242 C2220-2 0.166 -0.005 0.652 0.432 0.098 1.42 0.012 0.315 0.011 0.244
-C2220-2 0.165 0.004 0.662 0.442 0.097 1.42 0.013 0.315 0.011 0.243 J8L 0.165 0.011 0.651 0.430 0.097 1.41 0.017 0.299 0.011 0.245 J8L 0.168 0.007 0.649 0.436 0.096 1.43 0.013 0.304 0.011 0.246 J8L 0.165 0.009 0.653 0.437 0.098 1.41 0.014 0.318 0.010 0.246 Calculated Accuracy t% 5 10 6 5 5 2 15 5 15 15 Estimated Detection Limit, wt. 5 0.020 0.002 0.010 0.020 0.010 0.02 0.010 0.020 0.010 0.010 (a) Chemical analysis results taken from reference 16 (NEDO-24197 Revision 1 of October 1979) for the beltline plate C2220-2.
(b) A sample of material from the archive beltline plate C2220-2 sent to BCL from GE.
i savv a tu s - c o Lu m o u s 1
75 I i
within about five percent, the Mn agrees within about eight percent, the Ni agrees within about 12 percent, 5 and C agree within 20 percent, and Si ,
deviates the most by differing by about 30 percent. No comparison could be I made between Cr and V because these were not given in NEDO 29194.
j These data indicate the agreement between the plate C 2220-2 sample obtained from GE and the archive tensile specimen J8L obtair.ed from the Northern States Power Company, was very good and was within 1 to 3 percent for all elements except Y (13 percent) and P (45 percent). Agreement between chemical analysis results reported in NED0 24194 and those obtained at BCL was fair (within about 10 percent for all elements except S (20 percent) C (20 percent) and Si (30 percent). It must be noted that the analytical method and accuracies are not known for the chemical results reported in NED0 24194.
It is believed that variations of elements such as P, V, and Si can vary from point to point in any given plate. Therefore, based on these
! chemical analyses. It is concluded with a high degree of confidence, that the specimens with the prefix J were fabricated from the Monticello beltline base metalplate1-15(C2220-2,STP-1) 4 l
[
i s a v v s s. 6 s - c o t u m s u e
76 l
l
7.0 CONCLUSION
S Evaluation of the fast neutron dosimetry, chemical analysis, and mechanical property test (Charpy V-notch and tensile) results for specimens from the Monticello Nuclear Generating Plant surveillance Capsule 1 led to the following conclusions:
7.1 Neutron 00simetry ,
e The Monticello capsule and surveillance specimens at the 30 degree azimuthal location received a fast neutron fluence (E > 0.1 MeV) of 2.93 x 1017 n/cm2 as a result of operation from initial startup to November 1981(7.633EFPY).
e The Monticello pressure vessel azimuthal fluence (or flux) varied by as much as a factor of 4. The maximum fast neutron exposure occurred at about the 3 degree aziouthal position and the lead factor was only,0.31 for the pressure vessel inside surface. 0.41 for the 1/4T, and 1.05 for the 3/4T positions, e The maximum fast neutron fluence (E >1.0 MeV) at the pressure vessel 1/4T position was 7.20 x 10 17 n/cm 2 as a result of operation from initial startup to November 1981(7.633EFPY).
e Extrapolating the present data to the end of life (EOL) of 32 equivalent full power years (EFPY), the maximum calculated EOL 4
fastneutronfluence(E>1.0MeV)atthepressurevessel1/4T position would be 3.02 x 10 18 n/cm2 If a 20 percent accuracy is
!, assumed, the upper bound of the maximum E0L fast neutron fluence (E > 1.0 MeV) at the pressure vessel 1/4T position would be '
3.6 x 1018 n/cm2, o The E0L projected maximum fast neutron fluence (E > 1.0 MeV) of O 3.6 x 1018 n/cm2 at the pressure vessel 1/4T position is about 60 percent higher than the value of 2.2 x 1018 n/cm2 predicted by i the reactor vendor.
4
! .....<.-..o..
4 L
. . . . . - _ . - _ _ - .. - . _ _ . _ _ . _ - = . _ _ . - . - - . - _ . . - _
i . . .
i
- 77 -
1
! 7.2 Charoy l
f o After a fast neutron fluence (E > 1.0 MeV) of 2.93 x 1017 n/cm2, the irradiated Charpy V-notch specimens from the Monticello 30 4 degree surveillance capsule indicate a base metal upper shelf
- energy of 109 ft-lb, a weld metal upper shelf energy of
- j. 129 ft-lb, and a HAZ metal upper shelf energy of 118 ft-lb. .
These values are well above the minimum allowable upper shelf
{
energy of 75 ft-lb for unirradiated material and 50 ft-lb for r irradiated materials as specified in the current 10CFR50 l Appendix G.
l o Because of the lack of complete unirradiated data and, l especially, because of the capsule lead factors being much less j then one (instead of being greater than one), the shifts in j reference temperatures and drops in upper shelf energies were
{ determined using the capsule fluence results, chemical analysis i results for copper (0.17 weight 5) and phosphorus (0.01 j weight 5), and recommended practices outlined in Regulatory Guide
! 1.99.
! o Using Regulatory Guide 1.99, the limiting material as of l February 3, 1984 is the base metal with a shift in reference temperature of 42 F and an adjusted RTNOT of 56 F.
o Because of the high copper content of the base metal as compare'd
- to the weld s tal, the base material became the limiting material :
above a fast fluence of 7.8 x 1017 n/cm2 when using Regulatory Guide 1.99.
o using Regulatory Guide 1.99, the predicted end of life (EOL)
, shift in reference temperature for the base metal is 86 F l (assuming 40equivalentfullpoweryears(EFPY)ofoperation).
This yields an adjusted AT for E0L of 100 F, which is well NOT below the 200 F maximum permitted by 10CFR50 Appendix G.
t o The drop in upper shelf energies are predicted to be 30 ft-lb or less and results in an E0L upper shelf energy of 70 ft-lb or ,
above. This is well above the minimum E0L upper shelf energy of l
50 ft-lb as specified in 10CFR50 Appendix G.
e m n s 6 6 s - m e 6 u ns m u s
78 1 7.3 Tensile e All tensile test specimens exhibited ductile failures as evi-denced by the cup-and-cone type fracture shape.
e The tensile results are typical when compared with previous data generated at BCL for pressure vessel steels.
7.4 Chemistry e The irradiated weld metal specimens JKA, JEL, and JEP contained a maximum of 0.1 weight percent copper, a maximum of 0.01 weight percent phorphorus, and approximately 1.0 weight percent nickel.
e The unirradiated archive base metal spe':imens contained 0.17 weight percent copper, about 0.01 weight percent phosphorus, and approximately 0.65 weight percent nickel.
e The comparison of the chemical analysis results from the unirradiated archive plate (C 2220-2) and the unirradiated archive tensile specimen (J8L) agree very well.
e Based on these chemical analyses, it is concluded that the specimens with the prefix J were fabricated frem the Monticello beltline base metal plate 1 - 15 (C 2220-2 STP-1).
f
?
m arva tt s - co cu m mu m
) 79 ,
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
- Ductilit.y and Toughness S.ymposium, published by ;;ron and Steel Institute i of Japan (October, lyn), pp 259-319.
i 2. Steele, L. E., " Major Factors Affecting Neutron Irradiation Embrittlement of Pressure-Vessel Steels and Weldsents", NRL Report 7176 (October 30, 1970). <
i
- 3. Berggren, R. G., " Critical Factors in the Interpretation of Radiation Effects on the Mechanical Properties of Structural Metals", Welding l
Research Council Bulletin, 8,7,,1(1963).
- 4. Hawthorne, J. R., " Radiation Effects Information Generated on the ASTM
, Reference Correlation-Monitor Steels", American Society for Testing and i
Materials Data Series Publication DSS 4 (1974).
, 5. Steele L. E. and Serpan, C. Z. " Neutron Embrittlement of Pressure i Vessel Steels - A Brief Review", Analysis of Reactor Vessel Radiation r 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. Higgins, J. P. and Brandt, F. A., " Mechanical Property Surveillance of General Electric SWt Vessels", General Electric Report NED0-10115 (July,
, 1969).
! 8. " Standard Practice for Conducting Surveillance Tests for Light-Water i Cooled Nuclear Power Reactor Vessels", ASTM Designation E185-82, Annual 7
Book of ASTM Standards, Part 45(1982),pp888-896.
- 9. 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 i
j Energy to Nuclear International Power Plants Symp(osium Reliability Problems on Application of Reactor of Reliability PressureTechnology
- Components) in Vienna, Austria, and published in the Proceedings of that j Conference.
- 10. Proposed Research Program (Proposal No. 585-K-4189) on " Examination and Evaluation of Irradiated Surveillance Specimens from the Monticello Nuclear Generating Plant" to Northern States Power Company from Battelle Columbus Laboratories, January 16, 1981.
I 11. " Standard Methods and Definitions for Mechanical Testing of Steel
, Products" ASTM Designation A370-77, Annual Book of ASTM Standards, Part j 10(1982),pp28-83.
1 maves L6 s - c o Lu m m u s
80
- 12. ASME Boiler and Pressure Vessel Code,Section III, Appendix G for Nuclear Power Plant Components, Division 1, " Protection Against Nonductile Failure", 1983 Edition.
- 13. Code of Federal Regulation. Title 10. Part 50, Appendix G. " Fracture Toughness Requirements", May 27, 1983 Federal Register, pp 24008-24011.
14.- ASME Boiler and Pressure Vessel Code,Section III, Subsection NB (Class 1 Components) for Nuclear Power Plant Components, Division 1. NG-2330 and 2331. " Test Requirements and Acceptance Standards", 1983 Edition..
- 15. " Standard Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels". ASTM Designation E208-81, Annual Book of ASTM Standards,.Part 10 (1982), pp 420-439.
- 16. "Monticello Nuclear Generating Plant Information on Reactor Vessel Material Surveillance Program", General Electric Report NED0-24197, Revision 1. October 1979.
- 17. Private Communications, D. J. Brosche of Northern States Power Company to L. M. Lowry of Batte11e's Columbus Laboratory, November 4, 1982.
18.' Evaluated Reference Cross Section Library by R. L. Simons and W. N.
McElroy, BMWL-1312, May, 1970, Battelle Memorial Institute Pacific Northwest Laboratories, Richland, Washington 99352.
- 19. " Reference Cross Section Library for SAND II",~A C<nouter-Automited Interactive Met ud for Noutron Flux Soectra Determ< nation by Fo' 1 Activation. Asu.-TR-57-4L, Vol. III, Air Force Weapons Laboratory, Kirtland AFB, New Mexico, August, 1965.
- 20. RSIC Computer Code Collection. 007 3.5-Two Dimensional Discrete Ortinates Radiation Transmrt Code, Radiat'on shielding Enformation Center Oak Ridge National .aboratory, Oak Ridge. Tennessee November 17, 19f5.
- 21. CASK. 40 Grous Coucled Neutron and Ganna-Ray Cross' Section Data, R$!C Library DLC-23/CA5K, September, 1974.
- 22. Standard Methods for " Notched Bar Impact Testing of Metallic Materials".
ASTM Designation E23-82, Book of ASTN Standards, Part 10(1982),pp277-300.
- 23. Perrin, J. S., Fromm, E. 0., and Lowry, L. M., " Remote Disassembly and Examination of Nuclear Pressure Vessel Surveillance Capsules" Proceed-ings of the 25th Conference on Remote Systems Technology, American NuclearSociety(1977).
i
- 24. " Standard Methods of Tension Testing of Metallic Materials". ASTM Desig-nation E8-81, Annual Book of ASTM Standards, Part 10(1982),pp197-217. )
i i
marv e 66 s - m e 6u m au s
_ . _ _ . _ _ . _ _ _ . . _ ___ . 2
i
. o .
l 4
J 81
- 25. " Standard Recommended Practice for Elevated Temperature Tension Tests of 1 Metallic Materials", ASTM Designation E21-79, Annual ASTM Book of Stand-
] ards, Part 10 (1982), pp 267-276. !
1 1
- 26. " Standard Methoos for Chemical Analysis of Carbon Steel, Low Alloy Steel, 3 Silicon Electrical Steel, Ingot Iron, and Wrought Iron", ASTM Designation ,
i E350-82 (Sections 169 to 179 Entitled " Carbon, total, by the Combustion '
- Gravieetric Method"), Annual Book of ASTM Standards, Part 12(1982),pp
- 561-563.
l 27. The relative power data for the Monticello core were supplied in a letter from R. O. Anderson and Laura McCarten of Northern States Power Company ,
4 to Dr. Richard Jung of Batte11e's Columbus Laboratory, dated April 20, 1982.
- 28. " Standard Method for Measuring Neutron Flux, Fluence, and Spectra by
- Radioactivation Techniques" ASTM Designation E261-77, Annual Book of ,
j ASTM Standards, Part 45(1982),pp930-941. i i
- 29. " Standard Method for Determining Fast-Neutron Flux Density by Radioacti-
- Part4591982),pp951-956.
i l 30. " Standard Guide for Application of Neutron Transport Methods for Reactor [
- Vessel Surveillance", ASTM Designation E482-82, Annual Book of ASTM i Standards,Part'45(1982),pp1088-1092. .
! 31. " Standard Method for Calibration of Gerinanium Detectors for Measurement ,
!, of Gamma-Ray Emission of Radionuclides", ASTM Designation E522-78, Annual Book of ASTM Standards, Part 45(1982),pp1139-1144.
I 32. " Standard Method for Determining Fast-Neutron Flux Density by Radioacti-vation of Copper", ASTM Designation E523-82, Annual Book of ASTM Standards, Part 45(1982),pp1145-1152. l
- 33. Private communication, R. Strong of Northern States Power Company to A.
l M. Walters of Batte11e's Columbus Laboratory. November 20, 1982.
i
- 34. Private communication with G. H. Scott, Service Supervisor of General Electric Company to D. Musolf of Northern States Power Company, dated '
September 20, 1979. -
- 35. Letter from T. A. Ippolito of the NRC Operating Reactors Branch #2, Division of Licensing to L. 0. Mayer, Nuclear Support Services Manager of '
Northern States Power Company, Docket No. 50-263, dated July 16, 1981.
- 36. Kass, J. N., Giannuzzi, A. J. Hughes, D. A., Jones, R. D., and Hayes, T.
R.,"RadiationEffectsinBoilingWaterReactorPressureVesselSteels",
i ALicensingTopicalReport,NEDO-21708(77NE0168 Class!), October 1977.
- 37. Private communication, D. J. Brosche of NSP to L. M. Lowry of BCL, July 31, 1984, DRF 811-00255 and letter to D.includingenclosures(GEReportNSE0-54-0683, J. Brosche of NSP from G. H. Scott of GE, July 8,1983).
anvve66e-se6umaue !
l
.~ ,- _ _ - . _., __ _ _ _ , _ . , _ _ _ , . _ _ _ . _ , _ _ _ _ _ _ _ , _ _ _ _ _ , . _ _ , _ , _ . _ , ~ . _ , , _ _ _ , ~ . . _ . , .
Y
, a .
APPENDIX A INSTRUMENTED CHARPY EXAMINATION i
4 m ar v e 6 6 s - e m 6 u an a u s
A-1 APPENDIX A INSTRLM NTED CHARPY EXAMINATION Introduction The radiation-induced embrittlement of the pressure vessel of a comeercial nuclear reactor is monitored by evaluation of Charpy V-notch impact
- spechsens .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 l temperature and lateral expansion versus temperature can be drawn for a series
- of specimens of a given irradiated material tested over a range of tempera-ture. These curves, when compared to similar curves for the unirradiated l
l material, show the shift in behavior due to irradiation.
l '
Information in addition to the enery absorbed can be determined j from.a Charpy V-notch ispect test by instrumenting the equipment used to
! perform the test. 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(1,2,3).
The additional information obtained from the instrumented Charpy tes,tincludesthegeneralyieldload(psy)(plasticyieldingacrosstheentire
- crosssectionoftheCharpyspecimen),themaxfmumload(Psas),andthecrack
! arrest Ioed. In addition, if brittle fracture occurs, the brittle fracture l load (pF),andthetimetobrittlefracturecanbeobtained(seeFigureA1).
The area under the load-time curve corresponds to the total energy absorbed.
l which is the only data obtained in a normal uninstrumented Charpy test. The instrumented test, however, allo- separation of the energy abosrbed into (1) h
- theenergyrequiredforcrackinitiation(approximatedbythepremaximumload
{ gner y) (2) the energy required for ductile tearing (postmaximum load
{
e av v e 6 6 e - s e k u nn e u s I
, , . . . . . . . - - - . . _ _ _ . - . , . ~ , _ _ , _
r
. A .
A-2
- General Yielsi Leed, PGY Menimwn Leed, Penen Britife Freetwo Leed, Pp f
Creek Arrest Lead
%~
ima u~ e ._ E_. sk $__
C Thne to Brittle Frasewe =
Time Post *%Isuimwn Load" Energ
- j:j:j: Pwt settW*Prenw. Eaww FIGURE A-1. AN IDEALIZED LOAD-TIME HISTORY FOR A i
CHARPY IW ACT TEST m a r r e c t s - c a s. u m m u s
o o o .
A-3 energy), and (3) the energy associated with shear lip formation (postbrittle fracture energy), as shown in Figure A-1. Material properties, such as the yield strength and flow strength, appropriate to the loading rate of the Charpy impact test, may be subsequently calculated from the load nformation obtained by instrumenting the Charpy test (4). This information enhances the value of the relatively small Charpy specimens to reactor vessel surveillance programs. These procedures have received the endorsement of the technical connunity(5).
The instrumented Charpy test also gives the information shown in Figure A-1 as a function of tesperature, as.shown by the example in Figure A-2. Variousinvestigators(5-8)havedevelopedtheoriesthatpermita 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). The temperature corresponding to the intersection of the maximum or failure load curve and that of the general yield load in Figure A-2 is the temperature at which fracture occurs upon general yielding. Extended discussions of these fracture parameters can be found in the references indicated above.
Exnerimental Procedures The general procedures for the instrumented Charpy test are the same as those for the conventional impact test, and are described in the main text of this report. The additional data are obtained through a fairly simple electronic configuration, as shown in the schematic diagram of Figure A-3.
The striker of the 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 condi-tioned 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 marve 66 s - ce6u m mu s
r-e o .
A-4 4
b
% N s s, g , men
- Pp 5 C PF pgy b
1 .
Region 1 Reglen 2 Reglen 3 Reglen 4 Test Tempereewe i FIGURE A-2. GRAPHICAL ANALYSIS OF CHARPY IMPACT DATA mar rs 66 s - co6u m mu s
A-5 i
( "
)
.. 1 1 W "'
)
V ossies idridge aniones n n end V (/
Amplifier i
Shunt Triggering nesinense owies Hammer FIGURE A-3. DIAGRM OF INSTRUMENTATION ASSOCIATED WITH INSTRUMENTED CHARPY EXMINATION m a r v e i. i. s - c o L u na m u s
F
. o .
A-6 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 light beam device at the correct time to capture the amplifier output signal (3.4).
RESULTS AND DISCUSSIONS Specimens of three materials were tested. These materials are base metal (longitudinal orientation), weld metal, and heat-affected zone (HAZ) material. The instrumented Charpy results are presented in Tables A-1 through A-3. The tables list the specimen number, test temperature, impact energy, general yield load, maximum load, brittle fracture load, and crack arrest load. The load time curves are presented in Figures A-4 through A-6. 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 tables 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-7. The pertinent data used in the analysis of each record are the general yield load (Psy),themaximumload(Psax),thefast(brittle)fractureload(P),andthe F arrest load. The load-tanperature curves obtained for the three materials are shown in Figures A-8 through A-10.
I b
f marva 6La - eoou m au a
TABLE A-1. INSTRtNENTED CHARPY IWACT RESULTS FOR TE IRRA0!ATED SASE ETAL SPECIENS FROM THE MONTICELLO 30 DEGREE SLRVEILLAILE CAPSULE (The energy values listed are obtained from the impact machine dial.)
o .
4 Specimen Test Impact Energy General Yield, Maximum Load, Fast Fracture, Arrest Load, j Identification Teeperature, F ft-Ib Load PGY, Ib P ,,,, Ib Load, Ib lb h
0 JE3 0 7.0 3299 3299 3246 23 JOU 40 24.8 3140 4026 4010 256 [
o J0J 60 30.5 3033 4034 4034 594 c JE1 76 44.1 2988 4020 4020 734 l
C JOY J01 100 110 55.4 58.7 3061 2848 4274 4306 4211 4278 1544 1757 JE5 120 43.3 2821 4077 4077 1138 JCP 160 75.5 2777 4200 4101 2442 JE4 200 91.0 2639 4026 N/A N/A J04 300 110.0 2497 3947 N/A N/A JOS 350 103.0 2454 3813 N/A N/A J04 400 105.0 2383 3699 N/A N/A W
e 4 '
TABLE A-2. INSTRIMENTED CHARPY IMPACT RESULTS FOR THE IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE (The energy values listed are otstained from the impact machine dial.)
S Specimen Test Impact Energy General Yield, Maximum Load, Fast Fracture, Arrest Load, Identification Temperature, F ft-lb Load PGY, Ib P ,,,, Ib Load, Ib lb b JEK -80 24.5 3538 4290 4290 460 JEL -60 22.5 3368 4038 4034 185 y n JJE -40 68.7 3494 4487 3569 1327
$ JJP - -35 22.0 3380 3892 3880 819
~
C D68 -30 22.9 3451 4093 4093 488 o JEM -20 39.5 3274 4290 4259 1118
$ D57 -15 78.5 3475 4318 3G05 1438 JJ4 ~0 36.2 3222 4180 4176 721 JEP 0 65.2 3382 4377 4265 1987 JEY 20 75.8 3116 4184 3861 1875 JJT 76 96.0 2955 4014 3175 2100 JJ7 160 118.5 2777 4033 N/A N/A JEU 225 127.5 2761 3992 N/A N/A m -- - .
.\
TABLE A-3. INSTRLMENTED CHARPY IMPACT RESULTS FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE (The energy values listed are obtained from the impact machine dial.)
o Specimen Test Impact Energy General Yield, Maximum Load, Fast Fracture, Arrest Load, Identification Temperature, F ft-lb Load Pgy, lb P ,,,, Ib Load, Ib lb 4
$ JKD -79 19.5 3573 4144 4129 114 o JLE -60 28.5 3490 4400 4393 122 JKK -40 65.0 3408 4464 4272 1217 y JKA -30 71.3 3482 4668 4227 1847 JLC -20 40.0 3486 4160 4160 2352
{
E JKT -10 33.0 3522 4129 4125 1343 0
JLB 50.1 3408 4345 4298 2186 0 JL2 0 57.5 3211 4408 4389 1970 ,
JKM 76 110.2 2909 4031
- N/A N/A JLM 159 103.0 2775 3893 N/A N/A JLK 225 123.3 2785 4054 N/A N/A JK5 300 113.0 2529 3636 N/A N/A 072I ") 40 21.3 3104 3786 3786 673 (a) The notch was lccated a proximately 1/8 inches from the fusion line as determined by past-test etching. ASTM E185 specifies the notes be less than 1/32 inches from the fusion line.
9
1 e a ,
- A-10 i
l l l l 5806 l l l l SPECIMEN ND. e JES '
'8 4888 "
TEST TEMPERATURE (F) e
^
DIAL ENERGY, CFT-LBS) : 7 g GENERAL YIELD LDAD CLB) 3299 d MAXIMUM LDAD G 3290 2900- -
FAST FRACTURE LDAD G : 3248 "
ARREST LDAD CLS) : 23 15N"# '
a I l e l . l l l .
' s ses 1ses 1588 2888 TIME CMICRD-SECDM)S)
Sees l l l l l l l SPECIMEN ND. e JDU '
48 4888 "
TEST TEMPERATURE (F) :
^
l DIAL EIERGY, CFT-LBS) : 24.8 E.3 .
4
- GENERAL YIELD LDAD (LB)
- 3148 d i
4828 MAXIMUM LDAD (LB) e 2003--
FAST FRACTURE LDAD CLS) e 4818 .J
' ARREST LDAD CLB) 258 1988- I 8 l l l l l
. 1 1 -.
4 TIME (MICRD-SECONDS) .
4 5833 l l l l l l l SPECIMEN ND. : JDJ ""
SE 4888 "
l TEST TEMPERATURE CF) :
^ -
", DIAL EMRGY, CFT-LES) 38.5 ..
3ggg. ,
j GENERAL YIELD LDAD G.8) 3333 i
MAXIE34 LDAD G e 4834 2303- -
FAST FRACTURE LDAD G.8) s 4884 4 --
ARREST U)AD CLB) e 594 1833- I i
a l l l . , l l l
e ses 1ses ines asas i TIME 041CRD-SECONDS) i FIGURE A-4. INSTRUMENTED CHARPY IMPACT DATA FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE 7
4 CAPSULE i
mart s L L s - c o cu m n u s t i
.s .
A-11 l
l l 5e : : : : : : :
SPECIMEN NO. e JE1 TEST TEMPERATURE CF) 76- 4800 - -
DIAL EMRGY, CFT-LBS) 44. 1 G " '
GENERAL YIELD LOAD CLB) : 2988 MAXIMUM LDAD G e 4828 h 28W- - --
! FAST FRACT1stE LOAD CLB) s 4829 J ARREST LOAD @ s 734 18Es- I --
i e l l l l . r- r-a ses 1ses 15se asas TI M (MICRO-SECOfGS) 5308 l l l l l l l -
SPECIMEN NO. s JDY TEST TEMPatATURE CF) e les 48EE " "
DIAL EMRGY, WT-LBS) : ^
i 55. 4 3gg . . ..
GENERAL YIELD LOAD CLB) s 3081 MAXIML34 LOAD 2 s 4274 FAST F8tACTURE LOAD 2 s 4211 g g.
3 ARREST LOAD CLa) : .1544 1ses- W --
S l l l l l l 'l_
~
s ses taas 15ss 2sas TIME Ot!CRO-SECONDS) 580s l l l l l l l SPECIMEN NO. JD1 TEST 11MPetATURE CF) e 11s 48M ' '
l DIAL ENERGY, WT-LBS) : SS. 7 3333- -
i GENERAL YIELD LOAD 2 e 2348 MAXIISM LOAD CLB) : 4338 2SM- - --
FAST FRACT1NtE LOAD CLS) e 4279 I
AfutEST LOAD G s 1757 188s- "
=c_--
, -f-e ess less 24es sans TIM Od!CRO-SEcopes)
FIGURE A-4. (Continued) m ar v s L i. e - c o t u ew m u m
e o .
l A-12 i
i
{ 5808 l l l l l l l l SPECIMEN NO. e JE5 TEST TEMPERATURE CF) : 128' 4895 " "
^
UIAL ENERGY, CFT-LBS) : 43.3 l
- E gggg. . .. )
i GENERAL YIELD LDAD CLS) 2821 d i MAXIMIA4 LDAD CLB) 4877 2000- - --
l
- FAST FRACTURE LDAD CLB) s 4877 !
i' ARREST LDAD CLB) 1130 1838- "
S l l l ; . . .
S SOS ISOS 2488 3250 l TIME CMICRD-SECONDS) j 5000 l l l l l l l SPECIMEN NO. : JCP TEST TENTURE CF) e 188 48EE" "
i
^
DIAL ENERGY, CFT-LBS) : 75.5 CEMRAL YIELD LDAD CLB) s 2777 MAXIMAI LDAD Q.8) s 42SE g g.) ,,
FAST FRACTURE LDAD CLB) : 4181 3 ARREST LDAD CLB) e 2442 1859- "
S . . . . . . .
8 1M 2M 3M 4SM TIME CMICRO-SECDPCS)
SM l l l l l l l SPECIMEN NO. s JE4 TEST TEMPERATURE CF) e 288 4888 " "
DIAL ENERGY, CFT-LBS) s 81 GEMRAL VIELD LDAD CLB) 2830 o MAXIIEJM LDAD CLE) a 4828 l2355- --
FAST FRACTINtE LDAD CLB) : N/A 3 ARREST LDAD CLB) : N/A iM- --
S : . l l l 8 asse 4See .- -
Sees TIME CMICRD-SECDPOS) t-FIGURE A-4. (Continued) h i
s a r y s i. i. s - c a n.u na s u a
l A-13 sees l l l l l l l SPECIMEN NO. JDA TEST TEMPERATURE CF) : age 4888-- ..
DIAL ENERGY, WT- LBS) e ils ^ 1 GENERAL YIELD LDAD CLB) 2497 MAXIMUM LDAD CLB) 3947 0 2388-' ..
FAST FRACTINtE LDAD CLB) : N/A 3 ARREST LDAD CLB) : N/A 1m. ,,
g .
.N .r 8 2ges 433g 3333 gang TIME (MICRD-SECOM)S) 5800 l l l l l l l SPECIMEN ND. JD5 TEST TDe'ERATURE &) : 358 4WE" "
^
l DIAL EMRGY, WT-LBS) : 183
- 3mg. . ..
I GENERAL YIELD LDAD CLB) e 2454 1
MAXIMA 4 LDAD CLB) s 3813 g, ,, j FAST FRACM LDAD CLE) N/A l ARREST LDAD CLB) N/A im- --
8 l l l l ~l l l s v 4 ass -
esse TIM CMICRD-SECOMS) ,
l M l l l l l l l l SPECIMEN NO. s JD4 TEST TBE8ERATURE &) : 4M 48E" "
DIAL EERGY, FT-LBS) : 135 l
GE M RAL YIELD LDAD Q.8) e 2303 e I
MAXIMad LDAD Q.8) 3000 N/A g g, ,,
FAST FRACT13tE IJ3AD CL8) : .l
, ARREST LDAD CLB) : N/A iMS- "
l
\
g !
s asse 4ses esse eens TIME Od!CRD-SECOM)S) l
.4 FIGURE A-4. (Concluded) marv a t u s - c o tu m m u s
. .o I A-14 58se l l l l l l l SPECIMEN NO. s JEK TEST TEMPERATURE CF) e -88 4888 " "
DIAL ENERGY, CFT-LBS) : ^
24.5 E 3ggg.. .
GENERAL YIELD LOAD CLB) : 3538 d max! mum toAo Cun : 42es f g2,,,. . ..
FAST FRACTURE LDAD CLB) e 4298 J ARREST LOAD CLB) 488 1888- I ~
8- l l .- l l l l 8 588 1880 1588 2008 TIME (MICRO-SECONDS) 5888 l l l l l l l SPECIMEN NO. s JEL TEST TEMPERATURE CF) : -88 4888 " "
OIAL ENERGY, CFT-LBS) : ^
22.5 E gggg. . ..
GENERAL YIELD LOAD CLB) : 3388 d MAXIMUM LOAD CLB) s 4830 f
- g. . .,
FAST FRACTURE LOAD CLB) e 4834 J ARREST LOAD CLS) e 195 1M- I --
e-S b.
5W 1888 15N 2038 TIME CMICRO-SECOM)S)
Sees l l l l l l SPECIMEN NO. JJE TEST TEMPERATURE CF) : -48 4888 " "
DIAL ENERGY, CFT-LBS) : 88. 7 G l m 3002-- -
l GENERAL YIELD LOAD CLB) : 3494 d f
MAXIMUM LDAD CLB) : 4487 Q 2008- -
FAST FRACTURE LOAD CLB) : 3569 3 ARREST LDAD CLB) : 1327 1880- 1 -
2 l l l l l . .- =
0 500 1988 1588 2988 i
1 TIME CMICRO-SECONDS) i l FIGURE A-5. INSTRUMENTED CHARPY IW ACT DATA FOR IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE m A T T e s. L a - c o L u m m u s y e--r,-------c y.c,.-.,--m,_- - - , . - , - - - , , - - . , -
i t . = .
A-15 5888 l l l l l l l SPECIMEN ND. JJP l TEST TEMPERATURE CF) : -35 4208" -
DIAL ENERGY, CFT-LBS) : 22 G m 3000- --
GENERAL YIELD LDAD CLB) : 3382 d MAXIMUM LDAD CLB) : 3892 f Q 2998- --
FAST FRACTURE LDAD CLB) : 3880 3 ARREST LDAD CLB) : 819 1988- I --
2 l l . l l l l e See less 158e 2000 TIME CMICRD-SECONDS) 5809 l l l l l l l SPECIMEN ND. : DSB TEST TEMPERATURE CF) : -38 4888 ' "
l DIAL ENERGY, CFT-LBS) : 22.9 G m 33gg. . ..
GENERAL YIELD LDAD CLB) : 3451 d .
MAXIMUM LDAD CLB) : 4993 Q 2998-- --
FAST FRALM LDAD CLB) : 4893 3 ARREST LDAD CLB) : 488 1998- i --
8 9
W.
588 1888 1588 2988
' TIME CMICRD-SECDNDS) 5888 l l l l l l l SPECIMEN ND. : JEM 1EST TEMPERATURE CF) : -2g 4888- -
5 DIAL ENERGY, CFT-LBS) : 39.5 G m 3800 - -
GENERAL YIELD LDAD CLB) : 3274 d I
MAXIMUM LDAD CLB) : 4298 Q 2988-- --
FAST FRACTURE LDAD CLB) : 4259 3 k
ARREST LDAD CLB) : 1118 1988- I a l l l , . Y T-8 588 1990 1588 2988 TIME CMICRD-SECDNDS) 1 FIGURE A-5. (Continued) marv e tt s - c ocu m n u s
. o .
A-16 i
1 5888 l l l l l l I SPECIMEN ND. D57 TEST TEMPERATURE 7) : -15 4888~ ~
DIAL ENERGY, GT-LBS) 78.5 G un 3888- - --
l GENERAL YIELD LDAD CLB) 3475 d I
MAXIMUM LDAD CLB) : 4318 Q 2888-- --
FAST FRACTURE LDAD CLB) 3685 0 ARREST LDAD CLB) e 1438 1888- I --
8 l l l l l l l 8 588 1898 1588 2888 TIME CMICRD-SECDNDS)
Sees l l l l l l l SPECIMEN NO. : JJM TEST TEMPERATURE CF) : 8 488E" "
DIAL ENERGY, CFT-LBS) 36.2 G m 3888-- --
CENERAL YIELD LDAD CLB) 3222 d I i
MAXIMUM LDAD CLB) : 4188 Q o 2988--
FAST FRACTURE LDAD CLB) : 4178 J ARREST LDAD CLB) : 721 1888-1 "
8
, . %. . 1588 2388 8 SSB 1888 TIME (NICRD-SECONDS) t FIGURE A-5. (Continued) s a r v a t i. s - c o t u as s u s
l A-17 Sees l l l l l l l SPECIMEN NO. JEP TEST TEMPERATURE (F) : 9 4888 --
^
- , DIAL ENERGY, (FT-LBS)
- 65. 2 g ' '
GENERAL YIELD LOAD CLB) : 3382 d MAXIMUM LDAD CLB) 4377 Q 2988- d --
FAST FRACTURE LDAD CLB) 4265 3 ARREST LDAD CLB) 1987 1988- --
s l l l l- , r= l 8 800 1880 2488 3298 TIME (MICRO-SEcopCS) sees l l l l l l l SPECIMEN NO. e JEY TEST TEMPERATURE (F) 29 4888 " "
j
^
i DIAL ENERGY, CFT-LBS) : 75.B g ' '
[ GENERAL YIELD LDAD CLB) : 3116 d MAXIMLN LDAD CLB) : 4184 Q 2958 -
FAST FRACTURE LDAD (LB) e 3961 3
~
ARREST LDAD ' CLB) : 1875 1888- i ~
B l l l l l l l 8 See Isas 15ss ames TIME (NICRD-SEcopCS) t SMB l l l l l l l SPECIMEN NO. JJT TEST TEMPERATURE (F) 76 4888 "
DIAL ENERGY, (FT-LBS) 98 GENERAL YIELD LOAD Clip e 2955 c MAXIMUM LDAD CLB) e 4814 2SEE- - --
FAST FRACTtstE LDAD CLB) : 3175 .J ARREST LDAD CLB) : 2188 1M- -
a l l l l l l l s 2 1- 2ses Sees 4sse TIME (MICRO-SECOBOS)
-1 FIGURE A-5. (Continued) m ar r a i. L a - c o t u m m u s
e ... .
A-18 Sees l l l l l l l SPECIMEN NO. : JJ7 TEST TEMPERATURE CF) : 18e 4888 " "
^ '
DIAL ENERGY, CFT-LBS) : 118.5 g '
GENERAL YIELD LOAD CLB) : 2777 d MAXIMJM LOAD CLB) : 4MS 2ess- ' -'-
FAST FRACTURE LOAD CLB) : N/A a ARREST LOAD CLB) : N/A less- -
e l l l l l l l e less asse sees 4ees TIME CMTCRO-SECDICS) sees l l l l l l l SPECIMEN NO. i JEU TEST TEMPERATURE (F) : 225 4888 " "
^
DIAL ENERGY, CFT-LBS) : 127.5 g "
GENERAL YIELD LDAD CLB) : 2781 d MAXIMUM LDAD CLB) : 3e92 2see ' --
FAST FRACTURE LDAD CLB) : N/A ARREST LOAD CLB) : N/A less- ,
1 i
e : : : : : ,
e less 2ese sees dose TIME (MICRO-SEC0pCS) l 1
l FIGURE A-5. (Concluded) 1 l
marrects - cotu u su s e+ge =+q e--. -.'.wg.
e- y-e. g --
,--r - -.--.._,,,.--.--pyn , .,-,, . - - -g -.--_-,,-,-_-----,aw,, 7-m- . , .,.--.__,,,% -----.-.y. - - .- m.- ,m. _.we
> 80 D A-19 Sees l l l l l l l SPECIMEN ND. s JMD TEST TEMPERATURE (F) H MB " "
DIAL ENERGY, CFT-LBS) : 19.5 g " '
GENERAL YIELD LDAD (LID 3573 d MAXIMUM LDAD CLB) e 4144 g , ,,
FAST FRACTURE LDAD CLB) 4129 _1 ARREST LDAD CLB) 114 lage- I ..
i 8 l l l l l l s ses taas 15es asse TIME (MICRO-SECDDOS) 5833 l l l l l l l SPECIMEN ND. s JLE TEST TEMERATURE (F) : -Se 4888 " "
^
DIAL ENERGY, CFT-LBS) s 28.5 3ggg. . ..
GEPERAL YIELD LDAD (LB) s 340s
{
max! mum LDAD CLa) 44ss 2,,,. . ..
FAST FRACTURE LDAD CLB) 4303 ARREST LDAD CLB) a 122 130s- I --
a s
See h*l 1ses l l 15es l
2ses TIME (MICRO-SECDPOS)
Sams l l l l l SPECIMEN ND. e JMK TEST TEMPERATURE (F) e -48 4888 " "
DIAL ENERGY, CFT-LBS) : 85 GENERAL YIELD LDAD CLB) : 34Se c i
MAXIMLAd LDAD CLB) a 4484 2SEE- - --
FAST FRACTURE LDAD CLB) 4274
,d ARREST LDAD CLB) : 1217 15E I "
l
, . . . . . __r --
S Ses lage 158s 2Ss3 :
TIME (MICRO-SECDfCS) l I
i FIGURE A-6. INSTRUMENTED CHARPY IMPACT DATA FOR IRRADIATED HAZ METAL SPECIMENS FROM MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE is ar y a L L a - c o L u m us u s v -w,-e+--wwww =w=
O as s A-20 5ees l l l l l l l SPECIMEN NO. : JMA TEST TEMPERATURE (F) : -38 4898" -
DIAL ENERGY, (FT-LBS) : 71.3 ^
" ~
GENERAL YIELD LDAD CLB) : 3482 MAXIMUM LDAD CLB) : 4668 2sse- -
FAST FRACTURE LOAD CLB) : 4227 ARREST LOAD CLB) : 1847 1m. i ..
8 l l l l l l .
s ses taas 15es ases TIM (MICRO-SECODEIS)
SPECIMEN NO. : JLC TEST TEMPERATURE (F) : -28 4888 " "
DIAL ENERGY, (FT-LBS) : 48 G a 3898- -
f --
GENERAL YIELD LDAD CLID : 3486 d MAXIMUM LDAD (LB) 4108 Q 2988- - -
Q FAST FRACTURE LDAD CLB) : 4168 i ARREST LDAD CLB) : 2352- 1888M -
g j _. p .+ ._4 ; ; . ; -@d 9 588 1929 1588 2998 TIME (MICRO-SECONDS) 5888 l l l l l l l SPECIMEN ND. : JMT TEST TEMPERATURE (F) : -18 4888 " "
DIAL ENERGY, (FT-L9S) : 33 g "
GENERAL YIELD LDAD (LB) : 3522 cl MAXIMUM LOAD CLB) : 4129 290s- - -- l FAST FRACTURE LDAD CLB) : 4125 J ARREST LOAD CLB) 1343 1888- 1 "
s l l l l , ' ~ f-^ -- -
a ses 1ses 15es asse TIME (MICRO-SECONOS) i FIGURE A-6. (Continued) s ar v a s. c s - c o L u m m u s w- pve*w--e$w-y'V'-- --~*--'s---e -e-- - " * ' - ~ * = **e*
s . .
A-21 sees ,: l l l l l SPECIMEN NO. s JLB TEST TEMPERATURE (F) e -18 4888 " "
DIAL ENERGV, (FT-LBS) : 58. 1 g '
GENERAL YIELD LOAD (LB) : 3488 d MAXIMUM LOAD (LB) 4345 g g, ,,
FAST FRACTURE LOAD (LB) e 4298 '3 ARREST LDAD CLS) : 2106 lagg- -
8 l l . l l 8 SW 1888 2488 3298 TIME (MICRO-SECONDS) 5088 l l l l l l l SPECIMEN NO. e JL2 g 4888 "
TEST TEMPERATURE (F)
DIAL ENERGY, CFT-LBS) 57.5 .
3ggg. .
GENERAL YIELD LDAD CLB) e 3211 MAXIMUM LDAD (LB) 4480 --
h2SEE--l ^
FAST FRACTURE LDAD (LB) 4300 3 ARREST LOAD (LB) 1978 1988- I 8 l l l l l l .
s see 1sse 15es asse TIME (MICRO-SECONDS)
SCBS l l l l l SPECIMEN NO. s JMM 78 4888 "
TEST TEMPERATURE (F) :
DIAL ENERGY, CFT-LBS) 115.2 "
GENERAL YIELD LDAD (LB) : 2989 c MAXIMUM LDAD CLS) : 4831 -
h2938-FAST F8tACTURE LDAD (LB) : N/A J ARREST LDAD (LB) : N/A 1888- i B SM 1888 158B 2885 1
TIME (MICRO-SECONDS)
, FIGURE A-6. (Continued) marr a L L s - c o cu m n u s
a o. -
i A-22 2 :
58ee r l l l I I I SPECIMEN ND. s JLM TEST TEMPERATURE (F) 15G 4888" "
DIAL ENERGY, (FT-LBS) e le3 Gi
. m 3ess- - --
CENERAL YIELD LDAD CLB) 2775 d 4
MAXIMUM LDAD (LB) : 3893 --
h2988-FAST FRACTURE LDAD (LID N/A a ARREST LDAD (LB) : N/A 19ee- --
i l
e : l : l l l l e ines 2sse 3ese 4sse TIME (MICRD-SECONDS)
> 58ee l l l l l l l SPECIMEN NO. s JLK TEST TEMPERATURE (F) 225 4888" --
^ l
! DIAL ENERGY, CFT-LBS) : 123.3 GENERAL YIELD LDAD (LB) : 2785
, MAXIMLM LDAD (LB) : 4e54 2me- ..
FAST FRACTURE LDAD (LB) N/A a ARREST LDAD (LB) : N/A iges- ..
< a l l l , l l l
' e 2988 dese sees sees TIME (MICRD-SECONDS) i sese l l l l l l l SPECIMEN NO. e JK5 TEST TEMPERATURE (F) : See 4888 " "
DIAL EERGY, CFT-LBS) 113 g "
GIDetAL YIELD U3AD CLB) : 2529 d MAXIls.M LDAD G.8) : 3936 2See- - --
FAST FRACTURE LDAD (LB) N/A I ARREST LDAD G.9) e N/A 18es- -
e l l l l l l .
e 1ses asse same 4ase TIME (MICRO-SECONDS)
.1 1
i FIGURE A-6. (Continued) j i
s ar v s t a. a - c a s. u m o u s l
w .. .
1 A-23 sees l l l l l l l SPECIMEN NO. D72 48 4888 "
TEST TEMPERATURE (F) e
^
OIAL ENERGY, CFT-LBS) : 21.3 --
3ses -
GENERAL YIELD LOAD (LA) : 3184 MAXIMUM LOAD (LB) : 3786 2000- -
FAST FRACT1JRE LDAD (LB) : 3786 J ARREST LOAD (LB) 673 1988- i f "
a A# ,- --,
a see 1ses 1sse asas TIME (MICRO-SECONOS)
FIGURE A-6. (Concluded) i ,
l marv a tt s - ca tu m mu s
r -
a ee s A-24 Frosture Leed-Duplesoment Raw Type Cwves Data Romerks I Pp Brittle fresture g
I i
DeGestion II Brittle fresture l PGY I
l Deflection 111
] Pgy Brittle fresture followed try fresture 8
indientive of sheer lip formetson Deflection IV Seeses ereek propeastion h by Pgy, P,,,, unetsbie brittle frostuvo and fresture indieetive of sheer lip f... : --
Denestion ,
l V Pay, Stalde creek propegotion M by
]
a Pmex h imilestew of sheer lip Won Doneenen VI ]J Pay, Steide orsak propagation fonowed by i
Pmax 8'oss he Donession FIGURE A-7. THE SIX TYPES OF FRACTURES FOR NOTCHED BAR BENDING m arv a LL s - c c Lu m m u m
E E
m M D U D e o Y
> il d e o
r EEl-
_J m A
~ r
[
O 1.
I am
-( .,
~
A, O
n O @a
- O MAXIMUM LOAD c g jc e -
A O
GENERAL YIELD LOAD FAST FRACTURE-ARREST LOAD o
W - '
- 0 0 0 0 100 200 300 400 TEST TEMPERATURE F FIGURE A-8. INSTRUMENTED CHARPY LOAD VERSUS TEST TEWERATURE FOR IRRADIATED BASE METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE r
1 o
e.
- t i
i i k
i e
G l G ?
ic
. g l
i m
E -
tr B O @h w a O y e O i 4 -
E
- A
! 4 e o
r me me -
^-
i t
t r Jm ( 3 Q .
I I Q g' e g $
" ~
- r 3@ O MAXIMUM LOAD ;
~ A GENERAL YIELD LDAD l- E s O FAST FRACTURE-ARREST LOAD a
l 0 m -
j C H l 0 .
l l m - > - a c -
c -
l -100 8 188 200 300
! TEST TEMPERATURE F 1
I l
i FIGURE A-9. INSTRUMENTD CHARPY LOAD VERSUS TEST TEWERATURE FOR I IRRADIATED WELD METAL SPECIMENS FROM THE MONTICELLO ,
i 1
30 DEGREE SURVEILLANCE CAPSULE i i 4 i i___ .. -- -
a E
R
~
u O ge D BD A
I - g g o _
^ li 4 - l-a 4 g A
== - e .6 r Jm O -
e n y I c3 ca G n $g _
e 4 o
r JN e
- O MAXIMUM LOAD a
o 3 - A GENERAL YIELD LOAD C " O FAST FRACTURE-ARREST LOAD c .
.c .
c .
o
-100 0 100 200 300 TEST TEMPERATURE F "IGURE A-10. INSTRUMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR IRRADIATED HAZ METAL SPECIMENS FROM THE MONTICELLO 30 DEGREE SURVEILLANCE CAPSULE i 9
. - -_ = _. ._ - _ - _ - _ . - _ _ - _ - . . - - - _ _ -
4 . - , -
4 A-28 i
APPENDIX A REFERENCES (1) Wullaert, R. A., " Applications of the Instrumented Charpy Impact Test",
in Imoact Testino of Metals, American Society for Testing and Materials Special Technica' Publication 466, p. 148 (1970).
(2) 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).
(3) Ireland. D. R., " Procedures and Problems Associated with Reliable Control of the Instrumented Impact Test", in Instrumented Incact Tostino, i American Society of Testing and Materials Special Technica' Pub'ication 563, p. 3 (1973).
(4) Server, W. L., " Impact Three-Point Bend Testing for Notched and Precracked Specist.ns", Journal of Testing and Evaluation, 6_, 1, 29 (1978).
(5) Wullaert, R. A., editor, "C.S.N.I. Specialist Meeting on Instrumented Precracked Charpy Testing", Proceedings, Electric Power Research Institute (1980).
(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 and Steel Institute, E , 912 (1964).
(7) Tetelman, A. S. and McEvily, A. J., Fracture of Structural Materials, -
John Wiley and Sons Inc., New York (1967).
(8) Kobgashi, T., Takai, X., and Maniwa, H., " Transition Behavior and Evaluation of Fracture Tou hness in Charpy Impact Test", Trans. Iron and Steel Institute of Japan, ,115(1967).
t s av v a t i. s - c a s. u m m u s
_ . _ _