ML20108D848
| ML20108D848 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 05/15/1984 |
| From: | Failey M, Landow M, Lowry L Battelle Memorial Institute, COLUMBUS LABORATORIES |
| To: | |
| Shared Package | |
| ML20108D839 | List: |
| References | |
| BCL-585-84-3, NUDOCS 8412130443 | |
| Download: ML20108D848 (104) | |
Text
{{#Wiki_filter:BCL-585-84-3 I I FINAL REPORT on I EXAMINATION, TESTING AND EVALUATION OF IRRADIATED PRESSURE VESSEL SURVEILLANCE I SPECIMENS FROM THE VERMONT YANKEE NUCLEAR POWER STATION I to I YANKEE ATOMIC ELECTRIC COMPANY May 15, 1984 I by L. M. Lowry, M. P. Failey, M. P. Landow, D. Stahl, R. G. Jung, and R. S. Denning BATTELLE Columbus Laboratories I 505 King Avenue Columbus, Ohio .43201 Battelle is not engaged in research for advertising, sales promotion, or publicity purposes, and this report may not be reproduced in full or in part for such purposes. I SATTELLE -COLUMSUS gg2;gggagggg
I I LEGAL NOTICE I This report was prepared by Battelle Columbus Laboratories (BCL) as an account of sponsored research activities. Neither the Sponsor nor Battelle nor any person 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'cemposition disclosed in this report may not infringe privately owned rights; or assumes any I, 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.
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I l l l l l 1 BATTELLE - C O LU M a u s
I TABLE OF CONTENTS Page 1.0 SUM 4ARY ............................................................. I l 2
2.0 INTRODUCTION
3.0 SPECIMEN PREPARATION ................................................ 8 l 4.0 CAPSULE RECOVERY AND DISASSEMBLY..................................... 12 17 5.0 exPER1 MENTAL PROCEDURES.............................................. Neutron Dosimetry............................................. 17 5.1 5.2 Charpy Impact Properties...................................... 22 5.3 Tensile Properties............................................ 24 5.4 Chemical Analysis............................................. 25 5.5 Hardn'ess Tests................................................ 26 6.0 RESULTS AND DISCUSSION............................................... 27 6.1 Neutron Dosimetry............................................. 27 6.2 Charpy Impact Properties...................................... 40 6.3 Tensile Properties............................................ 59 t 6.4 Chemical Analysis............................................. 67 6.5 Hardness Tests................................................ 70 72
7.0 CONCLUSION
S.......................................................... 75
8.0 REFERENCES
I APPENDIX A A-1 INSTRUMENTED CHARPY EXAMINATION .......................................... APPENDIX A REFERENCES ................................ ................... A-26 l I I i I EATTELLE -COLUMBUS
I 1 LIST OF TABLES Page TABLE 1. INVENTORY OF CHARPY AND TENSILE SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE BASKET (" FAB" CODE)..... 15 TABLE 2. CALIBRATION DATA FOR THE HOT LABORATORY CHARPY IMPACT MACHINE USING APERC STANDARDIZED SPECIMENS ................... 22 TABLE 3. CROSS-SECTIONS FOR THE IRRADIATED FLUX MONITORS CALCULATED FROM FLUXES AT CAPSULE CENTER OF VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE.......................................... 32 TABLE 4. CONSTANTS USED IN DOSIMETRY CALCULATIONS FOR THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE......................... 32 TABLE 5. FLUX AND FLUENCE VALUES AT THE ENERGY GREATER THAN 0.1 MEV AT THE VERMONT YANKEE SURVEILLANCE CAPSULE (30-DEGREE AZIMUTHAL P0SITION)........................................... 34 TABLE 6. FLUX AND FLUENCE VALUES AT THE ENERGY GREATER THAN 1.0 MEV AT THE VERMONT YANKEE SURVEILLANCE CAPSULE (30-DEGREE AZIMUTHAL P0SITION)........................................... 35 TABLE 7. FLUX AND FLUENCE IN THE PRESSURE VESSEL WALL OF THE VERMONT YANKEE REACTOR-BEHIND THE SURVEILLANCE CAPSULE (30-DEGREE) I AND AT THE AZIMUTHAL ANGLE OF MAXIMUM FLUX IN VESSEL WALL (0-DEGREE)............................................... 36 TABLE 8. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE.......................................... 42 TABLE 9. CHARPY V-NOTCH IMPACT FOR RESULTS IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE.......................................... 43 l l TABLE 10. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED l HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE.......................................... 44 l TABLE 11. SUPEARY OF CHARPY IMPACT PROPERTIES FOR IRR'ADIATED i MATERIALS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE.......................................... 57 i TABLE 12. TENSILE PROPERTIES OF THE IRRADIATED MATERIALS FROM TME YERMONT YANKEE 30-DEGREE SURVEILLANCE CDSULE. . . . . . . . . . . . . . . . . 61 1 TABLE 13. TENSILE PROPERTIES OF THE UNIRRADIATED MMtRIALS lI l TABLE 14. FOR THE VERMONT YANKEE NUCLEAR POWER STATION.................. CHEMICAL ANALYSES RESULTS FOR VERMONT YANKEE BASE METAL AND WELD METAL SPECIMENS...................................... 68 69 11 l SATTELLE C O LU M B U S I
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I I uS10, muS (Continued) Page i TABLE 15. ROCKWELL HARDNESS TEST RESULTS FOR VERMONT YANKEE BASE AND WELD METAL SPECIMENS.......................... 71 TABLE A-1. INSTRUMENTED CHARPY IMPACT RESULTS FOR THE IRRADIATED I BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE.......................................... A-7 i TABLE A-2. INSTRUMENTED CHARPY IMPACT RESULTS FOR THE IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE.......................................... A-8 I TABLE A-3. INSTRUMENTED CHARPY IMPACT RESULTS FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE.......................................... A-9 E I I I I I I. I I 1 iii n ar r a L L s - c o tu m m u s
I LIST OF FIGURES FIGURE 1. VERMONT YANKEE CORE MIDPLANE SHOWING THE LOCATION OF THE 30-DEGREE, 120-DEGREE AND 300-DEGREE SURVEILLANCE CAPSULES........................................ 6 FIGURE 2. TYPICAL CHARPY V-NOTCH IMPACT SPECIMEN....................... 10 FIGURE 3. TYPICAL TENSILE SPECIMEN..................................... 11 FIGURE 4. VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE................ 13 FIGURE 5. TYPICAL CHARPY PACKET FROM THE VERMONT YANKEE 30-DEGREE SU m u u m CA,5U m ......................................... 1e I FIGURE 6. TYPICAL TENSILE TUBE FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCI CAPSULE......................................... 16
)E FIGURE 7. VERMONT YANKEE CORE, INTERNAL VESSEL STRUCTURES, AND VESSEL WALL GE0 METRY USED IN THE DOT CALCULATIONS............ 29 FIGURE 8. COMPARISON OF DOT SPECTRUM WITH FISSION SPECTRUM AT THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE................ 30 FIGURE 9. CALCULATED FLUX (E > 1 MEV) AT THE VERMONT YANKEE 30-DEGREE CAPSULE, INNER WALL, 1/4 THICKNESS, AND 3/4 THICK-I NESS AS A FUNCTION OF AZIMUTHAL ANGLE........................ 37 l
A FIGURE 10. FLUENCE AT 1/4 T AND 3/4 T POSITIONS AS A FUNCTION OF TIME FOR THE VERMONT YANKEE NUCLEAR REACTOR VESSEL........... 39 l FIGURE 11. CHARPY V-NOTCH IMPACT ENERGY VERSUS TEST TEMPERATURE FOR THE IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT I YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ 45 i FIGURE 12. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEMPERATURE FOR THE IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ 46 FIGURE 13. CHARPY V-NOTCH PERCENT DUCTILE SHEAR VERSUS TEST TEMPERATURE FOR THE IRRADIATED BASE METAL SPECIMENS FROM l THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE............ 47 FIGURE 14. CHARPY V-NOTCH IMPACT ENERGY VERSUS TEST TEMPERATURE FOR THE IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ 48 I FIGURE 15. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEMPERATURE FOR THE IRRADIATED WELD METAL SPECIMENS FROM THE VEPHONT i I YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ 49 BATTELLE -COLUMBUS L I
I I LIST OF FIGURES (Continued) Page FIGURE 16. CHARPY V-NOTCH PERCENT DUCTILE SHEAR VERSUS TEST TEMPERATURE FOR THE IRRADIATED WELD METAL SPECIMENS ! I FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE................................:..................... 50 1 FIGURE 17. CHARPY V-NOTCH IMPACT ENERGY VERSUS TEST TEMPERATURE FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ 51 FIGURE 18. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEMPERATURE FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ 52 FIGURE 19. CHARPY V-NOTCH PERCENT DUCTILE SHEAR VERSUS TEST TEMPERATURE FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE............ 53 FIGURE 20. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR THE I IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE............................... 54 FIGURE 21. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR THE IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE I 30-DEGREE SURVEILLANCE CAPSULE............................... 55 i h E FIGURE 22. CHARPY IMPACT SPECIMEN FRACTURE SURFACES FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE............................... 56 FIGURE 23. BASE METAL YIELD AND ULTIMATE TENSILE STRENGTHS VERSUS TEST TEMPERATURE FOR THE IRRADIATED TENSILE SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE....... 62 FIGURE 24. BASE METAL TOTAL ELONGATION AND REDUCTION IN AREA VERSUS TEST TEMPERATURE FOR THE IRRADIATED TENSILE SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE............ 63 FIGURE 25. POSTTEST PHOTOGRAPHS OF THE IRRADIATED BASE METAL TENSILE lI FICURE 26. SPECIMENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE)..... POSTTEST PHOTOGRIPHS OF THE IRP.ADIATED WELD METAL TENSILE 64 ! I SPECIMENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE)..... 65 FIGURE 27. I POSTTEST PHOTOGRAPHS OF THE IRRADIATED HAZ METAL TENSILE SPECIMENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE)..... 66 g V m AT T a L L s - c o LU M a u s
I LIST OF FIGURES I (Continued) Page FIGURE A-1. I AN IDEALIZED LOAD-TIME HISTORY FOR A CHARPY IMPACT TEST ................................................. A-2 FIGURE A-2. GRAPHICAL ANALYSIS OF CHARPY IMPACT DATA .................... A-4 FIGURE A-3. DIAGRAM OF INSTRUMENTATION ASSOCIATED WITH INSTRUMENTED CHARPY EXAMINATION ............................. A-5 FIGURE A-4. INSTRUMENTED CHARPY IMPACT DATA FOR IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE......................................... A-10 FIGURE A-5. INSTRUMENTED CHARPY IMPACT DATA FOR IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE......................................... A-14 FIGURE A-6. INSTRUMENTED CHARPY IMPACT DATA FOR IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE......................................... A-18 FIGURE A-7. THE SIX TYPE OF FRACTURES FOR NOTCHED BAR BENDING ........... A-22 FIGURE A-8. INSTRUMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ A-23 FIGURE A-9. INSTRUMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ A-24 FIGURE A-10. INSTRUMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR I IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE........................ A-25 l I ,I I . vi BATTELLE -COLUMeus l t I
I . I I FINAL REPORT on EXAMINATION, TESTING, AND EVALUATION OF IRRADIATED PRESSURE VESSEL SURVEILLANCE SPECIMENS FROM THE VERMONT YANKEE NUCLEAR POWER STATION to YANKEE ATOMIC ELECTRIC COMPANY I from I BATTELLE Columbus Laboratories by L. M. Lowry, M. P. Failey, M.P. Landow, D. Stahl, R. G. Jung, and R. S. Denning May 15, 1984 1.0
SUMMARY
A 30-degree azimuthal surveillance capsule assembly was received l l from the Vermont Yankee Reactor. The capsule was visually examined, opened, and the specimens inventoried. The basket contained a complete compliment of eight tensile specimens and 36 Charpy specimens. The 30-degree Vermont Yankee surveillance capsule marked 117C 4084 f G1 was irradiated for 7.54 equivalent full power years (EFPY) and was removed from the reactor after shutdown on March 4, 1983. Three iron, three copper, and three nickel neutron monitor wires from Charpy packets G1, G2, and G3 were !I I " " - - - " -
I I 2 analyzed. The capsule specimens received a fast neutron fluence (E > 1 MeV) of 4.30 x 10 16 n/cm2 . The calculated maximum fast neutron fluence at the 1/4 T pressure vessel wall position occurred at about zero degree azimuthal and was 3.78 x'1016 n/cm2 at the time the capsule was remov'ed from the reactor vessel. The capsule lead factor was 0.83 which indicates that the flux at the capsule slightly lags the flux at certain vessel wall positions. The maximum 1/4 T fast neutron fluence after 32 EFPY of operation was calculated to be 1.61 x 1017 n/cm2 (assuming a reactor lifetime of 40 years and 80 percent of full power operation at 1593 MWt )* Charpy impact specimens were tested to determine the impact behav-l ior, including the impact energy, lateral expansion, fracture appearance, and upper shelf energies for irradiated base metal, weld metal, and heat affected zone (HAZ) metal. The instrumented Charpy V-notch test results reported include load-time curves, general yield loads, maximum loads, brittle fracture I loads, and crack arrest loads for each of the base, weld, and HAZ metal speci-mens. The base metal exhibited the largest 30 ft-lb shift and therefore is the limiting material for the Vermont Yankee Reactor pressure vessel. The adjusted reference nil-ductility transition temperature (RTNDT) was calculated to be 79 F (initial RTNDT of 60 F plus the shift of 19 F) for the base metal at the maximum fast fluence pressure vessel location (0-degree) and at the pressure vessel 1/4 T position at the end of the capsule irradiation time on March 4, 1983. Using Regulatory Guide 1.99, the predicted maximum end of life (EOL) shift in RTNDT (assuming 32 EFPY) was estimated to be at most about 40 F for the Vermont Yankee Reactor pressure vessel base metal for the position of 17 2 maximum fluence (0-degree) and at the 1/4 T wall position (1.61 x 10 n/cm ), The predicted EOL adjusted RTNDT, therefore, is about 100 F. The base metal also exhibited the largest drop in upper shelf energy of 20 ft-lb to 128 ft-lb. The predicted EOL upper shelf energy, as estimated from Regulatory Guide 1.99, is not expected to fall below about 90 ft-lb. This is well above the minimum allowable EOL upper shelf energy of 50 ft-lb specified in 10CFR50 I Appendix G. The tensile properties of the irradiated specimens were deter-mined, including the yield and ultimate tensile strengths, as well as uniform and total elongations, and reductions in area. The Rockwell B hardness was I _ .. .m._.. . ... l
I 3 determined from indents made in three irradiated base metal and three irradi-ated weld metal specimens using a calibrated hardness tester. The halves of five broken weld metal Charpy V-notch specimens were analyzed for copper (Cu), nickel (Ni), and phosphorus (P) using the method of X-ray fluorescence. The base metal averaged 0.11 weight percent Cu, 0.68 weight percent Ni, and 0.014 weight percent P while the weld metal averaged 0.030 weight percent Cu, 0.95 weight percent Ni, and 0.013 weight percent P. I I I I I I E I. I lI l
- I B AT T E L L s - C O LU M a u s
I I
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 I evaluate radiation-induced changes in the material tensile, impact, and frac-tureproperties.(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 exposure. The impact properties as determined by Charpy V-notch impact tests generally exhibit an increase in the ductile-to-brittle transition temperature and a drop in the upper shelf in energy. I The Vermont Yankee Reactor is a boiling water reactor (BWR) designed by the General Electric Company (GE). The 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 meterial surveillance capsules con-taining appropriate specimens are placed into each comercial nuclear power reactor prior to initial startup. The purpose of the surveillance program I associated with each reactor is to monitor the changes in mechanical properties as a function of neutron exposure. The Vermont Yankee Generating Plant has a surveillance program which is described in reports issued by the General Electric Company.(7, 16) The program is based en ASTM E185 " Standard Practice for Conduct Surveillance ' Tests for Light-Water Cooled Nuclear Power Reactor Vessels", and was conducted using numerous other American Society for Testing and Materials lI (ASTM) and hnerican 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) I
- References are listed at the end of the text.
I I
I s I dosimeter wires, were inserted into the reactor pressure vessel prior to the initial startup of the Vermont Yankee Nuclear Reactor. Figure 1 shows the position of the three (30, 120, and 300-degree) capsules. I The American Society of Mechanical Engineers (ASME) Boiler and Pres-sure 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 pro-cedure is based on the principles of linear elastic fracture mechanics and is related to the reference nil ductility transition temperature (RTNDT)* The Code of Federal Regulations (13) requires that ' reactor vessels for which the predicted values of the adjusted RTNDT (initial RTNDT plus shifts due to irradiation) exceeds 200 F or the Charpy V-notch upper shelf energy is below 50 ft-lb at end of life, must be designed to permit a thermal annealing treatment at a sufficiently high temperature to recover material toughness properties-of ferritic materials of the reactor vessel beltline. RT is defined in reference 14, and is the higher of the nil-ductility NDT transition temperature (TNDT) determined by drop weight tests (15) and the Charpy V-notch test temperature (TCV) minus 60 F. TCV must not exceed TNDT + 60 F and be that temperature at which three Charpy V-notch specimens exhibit I not less than 50 ft-lb absorbed energy and at least 35 mils lateral expansion. Thus the reference temperature RTNDT is the higher of TNDT and TCV - 60 F. Tests of base metal, weld metal, and HAZ metal Charpy V-notch specimens must be conducted and the highest RTNDT used to. calculate the reference mode I stress intensity factor KIR. Startup and operation curves are generated based on the calculated X IR. At the time of initial operation of the reactor, the pressure-temperature operating curves were specified. During the life of the I reactor, the curves are to be revised to account for the changes in the Charpy impact behavior of the pressure vessel material due to irradiation. The adjusted pressure-temperature operating curves then allow for safe hydrostatic pressure testing, startup, and operation of the reactor. A previous report covers the prairradiation baseline tensile and Charpy impact properties of the three materials from the Vermont Yankee Reactor.(32) These materials include base metal, weld metal, and heat-affected-zone (HAZ) metal. The present report includes descriptions of the recovery and disassembly of the Vermont Yankee 30-degree surveillance, capsule I m ar r e t t a - c o cu m n u s
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180* I FIGURE 1. VERMONT YANKEE CORE MIDPLANE SHOWING THE I . LOCATION OF THE 30-DEGREE, 120-DEGREE, AND 300-DEGREE SURVEILLANCE CAPSULES I " " " - - "-"- n-.-.-, y n,_. , - - , - , . - . . , . -,. . . - , - - - - - - - - , - _ , , , _ . , . , _ , , , _ _ , , , , - - , , . - , , , , . - - - - - - - - - . - - - - - - _ _ _ - - - - - - - - - - - - - - - - - -
.I I 7 and the examination of the test specimens and dosimetry wires. This report also includes the procedures and results of the tensile, hardness, and Charpy impact tests and dosimetry and chemical analysis for the Vermont Yankee 30-l I degree surveillance capsule which was removed from the reactor during March of The BCL surveillance capsule quality assurance program is a plan-ning, controlling, surveillance, and documentation program to assure that all work is conducted following the basic principles 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 NB-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 quality assurance 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-I machines were periodically certified to ensure accurate and reliable results. A system of technical overchecks and independent quality assurance surveil-lance was used to insure compliance with the procedures and the overall quality assurance program. All personnel were trained and certified in compliance with ANSI N45.2.6 as being technically qualified for the task being undertaken and were aware of the quality assurance requirements. All data-generating instruments and apparatus were calibrated by I standards traceable to the U.S. Bureau of Standards. Specimen receipt and the packaging and shipment of. wastes for disposal are in accordance with the quality assurance program which is reponsive 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 (00T) and Nuclear Regulatory Commission (NRC) regulations at a properly licensed waste disposal site. Mechanical property specimens are being held for 6 months following receipt of the final technical report by Yankee Atomic Electric Company. marv a t t a - c o cu m n u s
I 8 3.0 SPECIMEN PREPARATION The base metal for the Vermont Yankee reactor pressure vessel is A533 Grade B Class 1 steel. Charpy V-notch and tensile specimens were prepared from an actual beltline plate (No. 2 shell and piece marked 1-14). The specimens were prepared from A533 steel plate (Heat No. C3017-2) provided by Lukens Steel Corporation in 1969. Base metal specimens were taken from I flat slabs cut parallel to both the plate surfaces at a depth of one-quarter and three-quarter plate thickness. The Charpy and tensile base metal I specimens were machined with their longitudinal axes parallel to the plate rolling direction and the Charpy specimen notches were cut perpendicular to the plate surface. Both Charpy and tensile base metal specimens were designated longitudinal specimens. The weld metal for the Vermont Yankee Reactor pressure' vessel was made according to Chicago Bridge and Iron Company Weld Procedure WPS-1 and welded using the shielded metal are process. The Charpy weld metal specimens I were machined in a direction transverse 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 1-1/16 inch from the weld root. The Charpy weld metal specimens' long axes were therefore parallel to the plate surface, and the notches were l cut perpendicular to the plate surface. The tensile weld metal specimens were composed entirely of weld metal and were obtained by machining the specimens l parallel to the weld length and parallel to the plate surf ace. The Charpy HAZ metal specimens were machined in a direction lI transverse to the weld length and parallel to the plate surface. The axes of l 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 HAZ metal specimens were machined transverse to the weld length ar.d parallel to the plate surface. The joint between the base metal and weld deposit was located at the center of the tensile specimen gage length. !I 'I
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B ! 9 i 3 A modifica' tion of a marking system developed by the U.S. Steel Corporation's Applied Research Laboratory (designated FAB Code) was used to mark one end of each surveillance Charpy and tensile specimen for later positive identification. A typical Charpy V-notch impact specimen is shown in Figure 2 and is a standard specimen design reconinended in ASTM E23-82 entitled " Standard Methods for Notched Bar Impact Testing of Metallic Materials". The typical tensile specimen design shown in Figure 3 conforms to recommendations in ASTM I E8-81 for subsize specimens. The ASTM E8-81 standard is entitled " Standard Methods for Tension Testing of Metallic Materials". I I I 1 I .5
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- 2. Grind reduced section and radii to 3y radii to be tangent to reduced section with no circular tool rnarks at point of tangency or wit *nin reduced section. Point of tangency shall not lie within reduced section.
I I FIGURE 3. TYPICAL TENSILE SPECIMEN g .. ..m.- _ ...
B-12 4.0 CAPSULE RECOVERY AND DISASSEMBLY 3 The surveillance capsule assembly was shipped from the Vermont Yankee Reactor site to the Battelle Columbus Laboratories (BCL) hot laboratory for postirradiation examination. Upon arrival at BCL on June 8, 1983, the I assembly was transferred to a hot cell for visual examination, serial number verification, photograohy, and disassembly. I The initial visual examination revealed no notable features. Two views of the capsule basket are shown in Figure 4. From these photographs, it appeared that the basked contained the expected four te'nsile tubes and three Charpy packets. The basket bore the serial number 117C 4084 Gl. The baskets bore the Vermont Yank'ee Reactor code number 24 and the basket code number 1, l which correspnds to the applicable group number, and is the same as the last digit in the basket serial number. The Vermont Yankee Reactor code number and basket code number appear as a binary code, as explained in Reference 7. The binary code numbers (drilled holes) appeared in the lower corners of the bas-I ket 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). (See Figure 4). The binary code identified this basket as coming from the 30-degree orientation. The basket was opened by cutting away the lower (spacer packed) end using a flexible abrasive cut-off wheel attached to a Mototool*. The basket did contain four intact tensile tubes and three Charpy packets. Identifi-cation numbers of the tubes and packets are listed below in the order of their location with the first being located at the top of upper basket and the last. being located at the bottom of the upper basket. The Charpy packets had both the binary code numbers and the alphanumeric identification, whereas the ten-sile tubes contained only a letter and a number stamped into one end of the plug. I
- Mototool is a trademark for a variable, high-speed motor attached to a I flexible shaft and chuck for grinding and cutting operations.
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FIGURE 4. VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE - 5 4 l N k BATTELLE - COLUMBUS I
I . Tensile Tube G1 Tensile Tube G3 Charpy Packet 117C 4083 G1 Tensile Tube G4
~
Tensile Tube G5 Charpy Packet 117C 4083 G2 Charpy Packet 117C 4083 G3
-I The three Charpy packets were also opened using the abrasive cut-off wheel to remove one end of the packet. The basket faces were separated I slightly with the fingers of the manipulator. The specimens were then removed by tilting 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)dosimeterwire. An inventory of the Charpy specimens is given in Table 1, and a total of 12 base metal,12 weld metal, and 12 HAZ metal l specimens were recovered. The four 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 I tensile specimens is also given in Table 1, and a total of three base metal, two weld metal, and three HAZ metal specimens were recovered, t I A photograph of a typical Charpy packet is shown in Figure 5. Similarly, a photograph of a typical tensile tube is shown in Figure 6. l3 l .I l l I I I 5ATTELLE -COLUMBUS l . .- . ._ .. _ _ .
l 15 ; TABLE 1. INVENTORY OF CHARPY AND TENSILE SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE l
~
CAPSULE BASKET (" FAB" CODE) Charpy Packets Gl(a) G2(b) G3(c) JC5 JJM JPC < JBJ JE5 JP4 I JDJ JKP JPB JB3 JJT JLD JBK JEU JP2 I JB1 JKE JKM JM6 JLT JBB JCA JJ7 JP3 JCC JJB JMD JBD JJL JL7 l JEC JP6 JBT JD1 JJ3 JPA Tensile Tubes Gl(a) G3(c) G4 G5 - I* JTJ JY3 JTU(a) JU6(b) JT3 JYJ JUJ(b) JY6(c) (a) Base metal specimens. l Weld metal specimens. i (b) t (c) HAZ metal specimens. l l lg . . . . - . _ . . .
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q lI i 'I I i' ~ . a ~~:u a n. . n n-0.75X A1120 g FIGURE 5. TYPICAL CHARPY PACKET FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE
- 5-
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)I fI All20 I FIGURE 6. TYPICAL TENSILE TUBE FROM THE VERK)NT YANKEE 30-DEGREE SURVEILLANCE CAPSULE t , t I (I g .. .. . ..
17 l I 5.0 EXPERIMENTAL PROCEDURES . I This section of the report describes the general procedures used to I 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 were performed atBatte11e'sColumbusLaboratories(BCL). All data evaluations were performed at BCL and the original data are recorded in Laboratory Record Book 38815. 5.1 Neutron Dosimetry I The Vermont Yankee surveillance basket 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 cell, ultra-I sonically cleaned in a water / soap solution, placed in a clean vial, and l transferred to the radiochemistry area for further cleaning and analysis. The wires were cleaned by wiping using successive swabs containing dilute acid (10 volume percent nitric for Cu and Ni and 25 volume percent hydrochloric for Fe), distilled water, and reagent alcohol until a negligible contamination l level was reached. The dosimeter wires were counted and wire data was generated. Depending on the wire activity, a suitable and representative sample was selected for counting. Dosimeter wires from Charpy packets G1, G2, and G3 i were weighted to an accuracy of + 0.0001 g using a calibrated (NBS traceable) analytical balance. The wires were then mounted and analyzed by gama ray I spectroscopy. Fast neutron flux and 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 following: I . I g ...m.
p - I 18 I Dosimeter Threshold Material Reaction Energy, MeV Half-Life l 1 Fe, pure 54Fe (n, p) 54Mn 2.5 312.6 days ! 63 Cu (n, a) 60Co 5.27 years Cu, high purity 6.1 Ni 58Ni (n, p) 58Co 2.1 71.2 days The ASTM procedures followed in the measurement of the monitor activities and I calculation of the neutron flux included: ASTM E261-77, " Measuring Neutron Flux, Fluence, and Spectra by Radioactivation Techniques" , ASTM E263-82, " Determining Fast-Neutron Flux Density by ~ Radioactivation of Iron" I ASTM E264-77, " Determining Fast-Neutron Flux by Radior:tivation of Nickel" I ASTM E522-78 " Calibration of Germanium Detectors for Measurement of Gamma-Ray Emission Rates of Radionuclides" ASTM E523-76, " Measuring Fast-Neutron Flux Density by Radio-I activation of Copper" ASTM E482-76, " Application of Neutron Transport Methods for Reactor Vessel Surveillance". The BCL premium, high resolution 50 cc high-purity germanium 60 detector,capableof2.0KeVresolution(fullwidth,halfmaximumat Co 1332 l 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 I (4096 channels). The integrated neutron fluence at the surveillance location was determined from the radioactivity induced in the irradiated detector materials. The gamma 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. I I - - - --
I I 19 I The activity A induced into an element irradiated for a time tj in a constant neutron flux is given by: I A = N[ c(E)$ (E)dE](1 - e~ *i) I where o(E) = the differential cross section for the activation reaction (barns)
$ (E) = the neutron differential flux (n/cm2 /sec)
N = the atom density of the target nuclei (atoms /g) A = the dacay constant of the product atom (sec-1). I If the sample is permitted to decay for a time t between g exposure and counting, then the activity when counted is:
~
A = N[ o (E)e (E)dE3(1-e-Ati) e~A** ,s If it is desired to find the flux of neutrons with energies above a given !g a energy level, Ec, the cross section corresponding to this energy level is i defined as: o(E)$(E)dE 0 o(E>Ec)= fg"+(E)dE g *ere ((E>Ec)= $(E)dE lI '- m Avv a L L s - c o Lu m e u s I l
1 I 20 Then l g
",(g),og,[.oW + m 7
- i I /Ec $(E)dE JEc $(E)dE
= o(E>Ec)+ (E>Ec)
I and th'e activity A may be written as: 1 A = N a(E)Ec) $(E>Ec) (1 - e# ) e'"W . The flux is'then computed from the measured activity as: A ,
$(E>Ec)=
I , N a(E>Ec) (1 - e-A ti ) e-Atw i To correct for fluctuations in power level, the flux is computed as:
# C N c(E Ec)C I
where ( C= f n ( g , ,- Aty ) ,. At"
- n=1 l
N = number of time intervals of constant flux l f = the fractional power level during interval n n tn = the time length of the interval n irradiation l tn = the time between the end of interval n and counting. g . . . . . . . . . . .
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-lgratedrelativepowervalueforeachmonthandforeachfuelassemblywasused 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 comunication.(26) B I g .....m.-_..
l I TABLE 3. CROSS-SECTIONS FOR THE IRRADIATED FLUX MONITORS l l l CALCULATED FROM FLUXES AT CAPSULE CENTER OF VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE Dosimeter Cross-Sections (Barns) l Material E > 0.1 MeV E > 1.0 MeV Fe 9.77 x 10-2 1.72 x 10-1 Cu 2.03 x 10-3 3.58 x 10-3 Ni 1.24 x 10-1 2.18 x 10-1 I I TABLE 4. CONSTANTS USED IN 00SIMETRY CALCULATIONS FOR THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSU,LE l Reaction Target, percent Isotopic Abundance, percent Threshold Energy, MeV Product Half-Life 5 54Fe(np)S4Mn 99.865 Fe 5.82 2.5 312.6 days I 63Cu(n a)60Co 99.999 Cu 69.17 6.1 5.27 years 58Ni(n.p)S8Co 99.927 Ni 67.77 2.1 71.2 days i I . I g .....m.-.. _ . .
) I !I . , Dosimetry Results The surveillance capsule was located at the 30-degree azimuthal position at approximately the core midplane position and about one inch from the inner pressure vessel wall. This capsule was in the reactor for 2755 equivalent full power days or about 7.54 equivalent full power years. The Vermont Yankee Nuclear Generating Plant design thermal output is 1593 MWt . The neutron monitor wires from Charpy packets G1, G2 and G3 were l counted to determine their specific activity. The recomended ASTM. l pr;cedures(27-31)werefollowedin'determiningthespecificactivityofthe wires. Each dosimeter monitor consisted of an approximately 4-inch length of tire which was rolled into a small coil for counting. The count rate was determined for each wire. The fast flux and fluence calculatt.d 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 March 1983 are given in Table 5 and Table 6, respectively, for each of the dosimeter wires along with the average of the flux and fluence derived from each wire and the average values for Fe, Cu, and Ni. In l addition,theaveragevaluesofthethreeresultsaregiven. Using the average fluxes of 3.18 x 10 8 n/cm2/ sec for E > 0.1 MeV and 8 n/cm2 see for E > 1.0 MeV, the fluxes at full power at the inside g1.80x10 / of the pressure vessel wall, at 1/4 T and.at 3/4 T directly behind the capsule (30-degree orientation) and at the maximum position ( 0-degree orientation) 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 . geactor pressure vessel lifetime of 40 years and the reactor operated at 80 pcreent of full power. The fine mesh and time integrated relative power values shown in Figure 7 for each fuel assembly was used in the 00r a 3 code to generate the values in Table 7. A plot of neutron flux (E > 1.0 MeV) as a function of azimuthal angle (in degrees) is shown in Figure 9. The fluence values at the maximum position for inner vessel wall, 1/4 T and 3/4 T are plottedasafunctionof'timeinequivalentfullpoweryears(EFPY)forthe Vermont Yankee pressure vessel in Figure 10. The lead factor, i.e., the ratio of the flux (E > 1.0 MeV) at the surveillance capsule to the largest flux l m arr e c t s - c o Lu m m u m
II 34 .l I I . TABLE 5. FLUX AND FLUENCE VALUES AT THE WITH ENERGY GREATER THAN 0.1 MEV AT THE VERMONT YANKEE SURVEILLANCE CAPSULE (30-DEGREE AZIMUTHAL POSITION) I Dosimeter Full Power Flux Material (n/cm2/sec) x 109 Fluence
- 17 (n/cm2)x10 Fe 3.086 7.346 3.204 7.627 3.086 7.346
~l Average of Fe 3.125 7.440 I Cu 3.238 3.444 3.216 7.709 8.197 7.655 Average of Cu 3.299 7.854 Ni 3.107 7.396 3.207 7.633 l Average of Ni 3.001 3.105 7.144 7.391 I Average of Fe Cu, and Ni 3.176 7.562 g*Fluencebasedon2755equivalentfullpowerdays.
I I I
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I g . . . . . . _ . . .
I 35 I !I l TABLE 6. FLUX AND FLUENCE VALUES AT THE WITH ENERGY GREATER THAN 1.0 MEV AT THE VERMONT YANKEE SURVEILLANCE CAPSULE (30-DEGREE AZIMUTHAL POSITION) I l Dosimeter Full Power Flux Flyence* Material (n/cm2/ sec) x 108 (n/:mZ)x1016 l l Fe(G1) 1.753 4.173 G2) 1.820 4.332 l G3) Average of Fe 1.753 1.775 4.173 4.226 (E ,W Cu 1.839 1.955 4.377 4.655 1.826 4.347 Average of Cu 1.873 4.460 l Ni 1.765 4.201 1.821 4.336 l G3) 1.705 4.058 'l Average of N1 1.764 4.198 l E Average of Fe, 1,.804 4.295 E Cu, and Ni
- Fluence based on 2755 equivalent full power days.
I I I I . g ..... . .. ...
Ms M M M M M M M M M M M M M M M TABLE 7. FLUX AND FLUENCE IN THE PRESSURE VESSEL WALL OF THE VERMONT YANKEE REACTOR - BEHIND THE SURVEILLANCE CAPSULE (30-DEGREE) AND AT THE AZIMUTHAL ANGLE OF MAXIMUM FLUX IN VESSEL WALL (0-DEGREE) M o 4 Fluence in Vessel f Full Power Flux in Vessel Behind Capsule (300) Maxir m (00) { Energy Location Behind Capsule (300) Maximum (00) Mar. 83 (1) E0L(2) Mar. 83 (1) E0L (2) (Mev), (n/cm2/ sec x 108 ) (n/cm2/ sec x 108) (x1016 n/cm2) (x1017 n/cm2) (x1016 n/cm2) (x1017 n/cm2) n a 0.1 Surface 2.04 3.85 4.85 2.06 9.16 3.89 c 0.1 1/4 T 1.83 3.52 4.35 1.85 8.38 3.55 j 0.1 3/4 T 0.953 1.82 2.18 2.26 2.32 0.962 0.987 4.33 5.19 1.84 2.20 c 1.0 Surface 0.977 1.0 1/4 T 0.712 1.59 1.69 0.719 3.78 1.61 1.0 3/4 T 0.285 0.623 0.678 0.288 1.48 0.629 l (1) Fluence based ~on 7.54 effective full power years. (2) Fluence based on 32 effective full power years. l l l t
I i 37 l 109
- I -
l l
~
1I l !I _ Capsule Flux at Full Power lI O surfees i l i .- i n' 1/4T i f 108 - 1 ' . i t E - I I _ 107 0 10 20 30 40 50 60 70 Aaimuthal Angle (deg.) FIGURE 9. CALCULATED FLUX (E > 1 MeV) AT THE VERMONT YANKEE 30-DEGREE CAPSULE, INNER WALL, 1/4 THICKNESS, I AND 3/4 THICKNESS AS A FUNCTION OF AZIMUTHAL ANGLE I -" ' - '"- "-
l iI (E > 1.0 MeV) received by the vessel wall at any azimuthal location, is 8 8 approximately 0.83 (1.80 x 10 /2.18 x 10 ) at the vessel surface. This result indicates t!iat the flux at the capsule actually lags the flux at certain vessel wall positions. The lead factors at the pressure vessel 1/4 T and 3/4 T positions were calculated to be 1.13 (1.80 x 108 /1.j9 x 10 8) and 2.89 (1.80 x 108 /6.23 x 107 ), respectively. The peak neutron fluence (E > 1 MeV) at the end of life (EOL) for the pressure vessel surface was predicted to be between 2.0 and 2.9 x 10 17 n/cm2 in the final report of May 23, 1975 by Southwest Research Institute on
" Vessel Material Surveillance Program for Vermont Yankee Nuclear Power Station". The BCL calculated surface EOL fast fluence value of 2.2 x 1017 n/cm2 agrees well with these previously reported values. The accuracy of the lfluencevaluesgeneratedatBCLisestimatedtobe120 percent. Although specific activities of fluence monitor wires can be determined to i 5 percent accuracies, uncertainties in neutron spectrum and spectrum averaged cross sections result in the larger variances in the computed flux and fluence values.
I I I : I BATTELLE -COLUMBUS
l 39 { 1018 I - I I - I s 1017 - ild I s ~ E ct 3/4T I E 1 1 I - 1016 - I ~f I I-103 0 5 10 15 36 Time (Full Power Years) FIGURE 10. FLUENCE AT 1/4 T AND 3/4 T POSITIONS AS A FUNCTION OF TIME FOR THE VERMONT YANKEE NUCLEAR REACTOR VESSEL I . I
.. .. ._..<e ...
I
~
) 40 6.2 Charpy Impact Properties Introduction A reactor pressure vessel receives a significant fast neutron exposure during operation and is therefore subject to radiation-induced l embrittlement. Charpy V-notch specimens were fabricated and irradiated in a Vermont Yankee surveillance capsule at the 30 degree azimuthal position and about one inch from the vessel wall. The specimens were then removed and tested. Appendix G of the ASME Boiler and Pressure Vessel Code, Section III,
- Division 1 (Nuclear Power Plant Components) 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 mechanics.
Analytical Method Charpy V-notch tests were conducted over a range of temperatures. The impact energy, lateral expansion, and fracture appearance for the I irradiated specimens were determined from the tests which followed ASTM procedures.(22) Plots of impact property versus test temperature were plotted for each type of specimen (base metal, weld metal, and HAZ metal) using the I hyperbolic tangent fit. From these data, the temperatures at which 30 ft-lb, 50 ft-lb, and 35 mil lateral expansion occurred were determined and the upper shelf energy for each type of specimen was also determined. I .. .m.- _ e....
.g I '
41 Charpy Impact Test Results 3 Twelve irradiated base metal Charpy V-notch impact specimens, twelve irradiated weld metal Charpy V-notch impact specimens, and twelve irradiated HAZ metal Charpy V-notch specimens were tested. The results of tests con-ducted between 0 and 320 F for the base metal specimens are listed in Table 8. The results of tests conducted between -80 and 320 F for the weld metal specimens are listed in Table 9 and the results of tests conducted between -80 and 320 F for the HAZ metal specimens are listed in Table 10. In addition to the total impact energy values, the measured lateral expansion values and the ostimated fracture appearance for each specimen are also listed in Tables 8, 9 a and 10. The total impact energy is the amount of energy aosorbed by the specimen tested at the indit:ated temperature. Lateral expansion is a measure of the plastic " shear lip" deformation produced by the striking edge of the impact machine hamer when it impacts the specimen. Lateral expansion is determined by the change of specimen thickness directly adjacent to the notch location. Fracture appearcnce 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, laterai expansion, and fracture appearance) versus test temperature are graphically illustrated in Figures 11 through 19. These figures show the change in impact properties as a function of temperature. Figures 20, 21, and 22 show the fracture surfaces of the Charpy specimens. A sumary of the Vermont Yankee surveillance capsule Charpy 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 11.* I OText continued on page 58. EATTELLE -COLUMBUS
l l 42 I I 1 I TABLE 8. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE I Specimen Test Impact lateral Fracture Identification I Temperature, F Energy, ft-lb Expansion, mils Appearance, Percent Shear JB1 0 12.5 14.0 10 JBK 10 28.0 26.2 20 JBT 20 17.5 19.6 15 JB3 20 32.0 28.8 20 JCC 40 35.0 33.6 20 J01 50 50.5 41.4 25 JBB 60 54.0 45.8 35 JBJ 80 76.0 59.8 55 JBD 120 92.0 71.2 70 160 124.0 88.8 I JCA 100 JDJ 240 127.0 90.0 100 JC5 320 128.0 88.8 100 Ik Instrumented results are contained in Appendix A, Table A-1. I I I I -- - -
1 l I TABLE 9. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE I Specimen Test Impact Lateral . Fracture Identification I Temperature, F Energy, ft-lb Expansion, mils Appearance, Percent Shear JE5 -80 28.0 22.8 25 JKP -40 29.0 27.0 30 JEU -30 44.0 40.2 40 JJL -20 49.0 43.2 40 JKM 0 30.0 28.8 30 JJT 0 55.5 51.2 45 JJ7 19 67.0 54.8 60 < JJB 40 68.5 58.8 60 JKE 80 99.0 77.0 80 91.8 I JEC JJ3 160 240 120.5 121.0 93.8 - 100 100 , JJM 320 114.5 89.8 100 (a) Instrumented results are contained in Appendix A, Table A-2. I I I I I ... . . - . _ . . .
44 I
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I I TABLE 10. CHARPY V-NOTCH IMPACT RESULTS FOR IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE Specimen Test Impact lateral Fracture Identification Temperature, Energy, Expansion, Appearance, F ft-lb mils Percent Shear JPA -80 11.5 9.8 10
-40 23.0 19.4 I
JP3 15 JLT -20 12.5 13.6 15 JL7 -20 63.5 50.8 60 JP6 0 15.0 15.6 20 JP2 0 45.5 40.8 50 JLD 20 40.5 39.6 45 JP8 40 70.5 56.2 70 JP4 80 56.5 48.2 60 JM6 160 105.5 78.4 100 I JPC JMD 240 320 116.0 112.5 87.0 87.6 100 100 (a) Instrumented results are contained in Appendix Table A, Table A-3. SATTELLE -COLUMBUS
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-100 TEST TEMPERATURE F s FIGURE 12. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEMPERATURE FOR l THE IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT l YANKEE 30-DEGREE SURVEILLANCE CAPSULE l l
M M M M MM M M M M m m m M M M M M M I N O
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. FIGURE 13. CHARPY V-NOTCH PERCENT DUCTILE SHEAR VERSUS TEST TEMPERATURE FOR Tl;E IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE
= === - - - u M M M M M M-M M M M M M M M M M M l
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-100 TEST TEMPERATURE F FIGURE 14. CHARPY V-NOTCH IMPACT ENERGY VERSUS TEST TEMPERATURE FOR THE IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILtANCE CAPSULE
nas . men amm num uma muu num man um um num ams mum num i m 5 O m
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-100 TEST TEMPERATURE F FIGURE 17. CHARPY V-NOTCH IMPACT ENERGY VERSUS TEST TEWERATURE FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE l
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-100 TEST TEMPERATURE F FIGURE 18. CHARPY V-NOTCH LATERAL EXPANSION VERSUS TEST TEMPERATURE FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE
~
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=
FIGURE 20. CHARPY IWACT SPECIEN FRACTURE SURFACES FOR TE IRRADIATED
- BASE ETAL SPECIENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE
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- i. - - - - - ......
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TABLE 11.
SUMMARY
OF CHARPY IMPACT PROPERTIES FOR IRRADIATED MATERIALS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE E > 1.0 MeV 30 ft-lb 50 ft-lb 35-Mil Lateral bpper Shelf Fluence, Transition Transition Expansion Energy, m Material n/cm Temperature, F Temperature, F Temperature, F ft-lb j 52 35 148 l
) Base 0 8,
-35 -45 107 f Weld 0 -50
-10 110 l HAZ 0 -30 13 C
i 16 60 40 128 n Base 4.30 x 10 27 16 -5 -28 122 l h Weld 4.30 x 10 -45 16 35 5 117
! HAZ 4.30 x 10 -15 a
c o Base change 19 8 5 -20 change 5 30 17 15 Weld 22 15 7 HAZ change 15 i
k I 58 Unirradiated archive baseline Charpy V-notch impact data were obtained by Battelle for material from the base, weld, and HAZ metal locations.(33) The 30 ft-lb, 50 ft-1b, and 35-mil lateral expansion index temperatures were obtained, as well as the upper shelf energy. These data are also given in Table 11. By difference, the shift in transition temperatures can be calculated for each index. The shift or changes in 30 and 50 ft-lb transition temperatures, 35-mil lateral expansion temperature, and upper shelf energy are also given in Table 11. The shifts range from 5 to 30 F. The upper shelf energy for the base metal has dropped 20 ft-lb to 128 ft-lb. However, the predicted EOL upper shelf energy .as estimated from Regulatory Guide 1.99, is not expected to drop below 90 ft-lb. This is well above the minimum allowable EOL value of 50 ft-lb specified in 10 CFR 50 Appendix G. The initial reference nil-ductility transition temperature (RTNDT) -
~
was established previously for the Vermont Yankee unirradiated base and weld metals as 60 F I ) The most recent Nuclear Regulatory Comission (NRC) ruling (May 27,1983) for Appendix G to 10 CFR 50, " Fracture Toughness Requirements for Light-Water Nuclear Power Reactors", specifies that an adjusted RT for irradiated specimens can be determined by adding to the NDT initial RT NDT the amount of temperature shift measured at the 30 ft-lb level in the average Charpy curve for the irradiated material relative to that of the unirradiated material. The material with the largest measured reference temperature shift is then the limiting material. The Vermont Yankee pressure vessel base metal exhibited the largest 30 ft-lb shift (19 F) and therefore is the limiting material for this reactor. The adjusted RTNDT was calculated by adding the initial reference temperature to the 30 ft-lb shift and was found to be 79 F (60 F + 19 F) for the 30-degree surveillance capsule specimens. Because the surveillance capsule lead factor is greater than one (1.13) for the maximum fluence location (0-degree) and at the pressure vessel 1/4 T position, the value of 79 F for the adjusted RTNOT is conservative. This adjusted reference temperature can be used in revising the plant pressure-temperature operating curves. Using Regulatory Guide 1.99, the predicted end of life (EOL) shift in RTNDT (assuming 32 EFPY) was estimated to be at most about 40 F for the pressure vessel maximum fluence position and at the 1/4 T call position. This compares exactly with the predicted lifetime shift of NATTELLE -COLUMBUS
59 l 40 F found in the Southwest Research Institute Final Report of May 23, 1975,
" Vessel Material Surveillance Program for Vermont Yankee Nuclear Power
! Station". 6.3 Tensile Properties Introduction The tensile specimens were irradiated in the Vermont Yankee surveillance capsule which was located at the 30 degree azimuthal position and about 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 irradiated materials were determined. Analytical Method Prior to testing, each tensile specimen diameter was measured using a blade micrometer and an initial cross-sectional area 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 one inch gage section and was verified by posttest measurements of the increase in distance between the tensile specimen punch marks (originally positioned one inch apart). The yield load and ultimate 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 posttest cross-sectional area from the
, initial cross-sectional area, dividing by the initial cross-sectional area, and multiplying by 100. The fracture strength was calculated by dividing the failure load by the pretest cross-sectional area and the fracture stress was calculated by dividing the failure load by the posttest cross-sectional area.
BATTELLE -COLUMBUS
Tensile Test Results The tensile test parameters and irradiated specimen tensile properties are listed in Table 12 and plotted in Figures 23 and 24. This table lists the specimen number, material, and test temperature. Also listed are the 0.2 = parcent 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 25, 26 and 27. 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. Tensile tests were conducted at room temperature (75 F), 180 F, and 543 F. All three materials, base metal, weld metal, and HAZ metal exhibited decreases in yield strength, ultimate strength, and fracture strength when the test temperature was increased from room temperature to 180 F. These tensile properties appear, however, to recover partially (and in some cases totally) at the test temperature of 543 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 543 F for all three material types. The percent reduction in area for the three materials was relatively constant at test temperatures of 75 F (room temper-ature) and 180 F but decreased slightly (6 to 13 percent) at a test temperature of 543 F. Within experimental standard deviation, the uniform elongation and total elongation appear to decrease when the test temperature was increased from
*15 to 180 F and appears to recover at the test temperature of 543 F.
- Text continued on page 67.
BATTELLE -COLUMEUS
TABLE 12. TENSILE PROPERTIES FOR THE IRRADIATED MATERIALS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE D
-f " Test Fracture Reduction Temp.ll) Stress in Area Elongation, percent (2)
E Specimen Material Strength, psi e No. Type (F) Yield Ultimate Fracture (psi) (percent) Uniform Total I 8.6 21.2 JTJ Base RT 65,820 91,120 58,470 191,000 69.4 , o ~ O JTU Base 180 62,500 86,790 54,880 180,000 70.0 8.4 20.0 c JT3 Base 543 60,850 87,930 60,850 184.000 67.0 9.9 2'0.5 172,100 68.6 6.2 20.5 fC JU6 Weld RT 72,760 86,020 76,020 54,080 49,800 155,100 68.0 7.1 22.9 JUJ Weld 543 57,520 JY3 Haz RT 70,770 87,270 52,550 187,000 72.0 6.8 19.6 JYJ Haz 180 66,630 80,310 49,690 175,200 72.0 6.0 18.2 JY6 Haz 543 63,520 84,650 58,130 166,300 65.0 6.4 21.6 I (1) Room temperature (RT) is approximately 75 F. (2) The elongation is for a 1-inch gauge length.
) 62 ) s 100 5 Ultimate Strength (irradiated)
$ 0.2% Yield Strength Utrediated) 91.1 90 - 87.9 58 80 -
9 5 .= a 70 - 65.8 60.9 60 I I I i i 50 100 200 300 400 500 600 0 Test Temperature (F) FIGURE 23. BASE METAL YIELD AND ULTIMATE TENSILE STRENGTHS VERSUS TEST TEMPERATURE FOR THE IRRADIATED TENSILE SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE BATTELLE -COLUMBUS
63 100 ( A Reduction in Area (irradiated) 3 Total Elongation (Irrediated) 69.4 70.0 (
= so -
t . 1 E l
].0 -
232 ,o o 2gs ( a -
=
[ I I I l o I 0 100 200 300 400 500 600 Test Temperature (F) FIGURE 24. BASE METAL TOTAL ELONGATION AND REDUCTION IN AREA VERSUS TEST TEMPERATURE FOR THE IRRADIATED TENSILE CPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE BATTELLE -COLUM5us
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JT3 (543 F) A-1167 & -1173 FIGURE 25. POSTTEST PHOTOGRAPHS OF THE IRRADIATED BASE ETAL TENSILE SPECIENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE) BATTELLE -COLUMDuS
I e 65
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JUJ (543 F) A-1168 & -1171 FIGURE 26. POSTTEST PHOTOGRAPHS OF THE IRRADIATED WELD ETAL TENSILE SPECITNS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE) BATTELLE -COLUMBUS
I i 4 66
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JY6 (543 F) A-1170 & -1169 1 I : FIGURE 27. POSTTEST PHOTOGRAPHS OF THE IRRADIATED HAZ ETAL TENSILE
^
SPECIENS SHOWING BOTH THE REDUCED AREAS AND FRACTURE SURFACES (VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSil.E) l 1 i I l e ar r a c c e - c o cu m e u. l
i
/
67 These tensile data can be compared to the baseline data given in l Table 13. The data compare favorably for the base, weld, and HAZ metal, indicating that there is essentially no reduction in tensile properties as a l j result of the neutron exposure to date. l 1 6.4 Chemical Analysis i 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 I 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, nickel, and phosphorus on the reference nil-ductility (transition) temperature (RTNDT) as a function of fluence. In order to use this guide or to establish the copper, nickel and phosphorus content, a chemical analysis must be performed. In addition, base metal chemistry must be determined. The method of X-ray fluorescence (XRF) was used to determine the copper (Cu), nickel (N1), and phosphorus (P) contents of the base and weld I metal specimens. Five irradiated base metal and five irradiated weld metal samples consisting of broken halves of a tested Charpy V-notch specimen were I analyzed for Cu, Ni, and P content. The analytical results for the smaples are listed in Table 14. Some Analyses were run in duplicate and the values for each run are given in Table 14. The calculated accuracy for this X-ray fluorescence chemical analysis is 1 15% for copper, 1 6.0% for nickel, and i 10% for phosphorus. The estimated detection limit is 0.02 weight percent for copper and 0.01 weight percent for both nickel and ;:hosphorus. l The results of samples of broken unirradiated baseline Charpy }i specimens were obtained earlier. Thesa data are also shown in Table 14. The chemical analysis results af unirradiated samples reported in the October 1977 l General Electric Report NEDO-21708 are also listed for comparison. All results are similar, as expected, within the error bands noted above. I mATTELLE -COLUMBUS
M M TABLE 13. TENSILE PROPERTIES OF THE UNIRRADIATED MATERIALS FOR THE VERMONT YANKEE NUCLEAR GENERATING PLANT 1 i
- o
< 4 d Tesh Fracture Reduction fr Specimen Material Temp.La) Strength, psi Stress in Area Elongation, percent (b) No. Type (F) Yield Ultimate Fracture (psi) (percent) Uniform Total a i JTl Base RT 64,390 89,490 56.120 196,430 71.4 10.0 24.1 n 84,830 52,950 184,400 71.3 8.9 20.0 E JTD Base 180 61,910 r JTK Base 543 61,610 89,100 63,140 163,160 61.3 9.0 20.6 g Jul Weld RT 68,000 82,000 50,100 182,840 72.6 10.2 26.9 U JUD Weld 543 67,620 85,340 54,990 169,810 67.6 8.9 21.2 0 JYC HAZ RT 68,090 88,210 53,860 194,850 72.4 6.8 21.7 , JYP HAZ 180 65,620 83,980 60,850 156,250 61.0 6.9 16.7 JYU HAZ 543 64,500 83,770 57,810 164,740 65.0 6.0 23.5 (a) Room temperature (RT) was approximately 80 F.
- 3 (b) The elongation is for a 1-inch gage length.
69 I TABLE 14. CHEMICAL ANALYSES RESULTS FOR VERMONT - YANKEE BASE AND WELD METAL SPECIMENS I Specimen Material Elements, Weight Percent No. Type Cu Ni P I JDD Base (U) 0.11 0.66 0.020 J00 0.11 0.66 0.020 I JDE Base (U) Base (U) 0.11 0.71 0.011 JDE Base (U) 0.10 0.71 0.013 (a) Base (U) 0.10 0.66 0.020 l ~ JB1 JB1 Base (I) Base (I) 0.11 0.10 0.68 0.67 0.019 0.010 JBK Base (I) 0.10 0.70 0.014 JBT Base (I) 0.10 0.68 0.010 I JB3 JCC Base (I) Base (I) 0.10 0.10 0.65 0.66 0.010 0.014 JCC Base (I) 0.10 0.69 0.010 JJP Weld (U) 0.030 0.91 0.013 JJP Weld (U) 0.035 0.93 0.013 JKT Weld (U) 0.030 0.93 0.013 l JKT (a) Weld (U) Weld (U) 0.030 0.010 0.93 0.95 0.010 0.012 I JE5 Weld (I) 0.024 0.94 0.012 JE5 Weld (I) 0.027 0.95 0.013 I JKP Weld (I) 0.035 0.88 0.010 JEU Weld (I) 0.027 1.01 0.013 JJL Weld (I) 0.027 1.03 0.023 JKM Weld (I) 0.030 0.96 0.010 JKM Weld (I) 0.038 0.93 0.016 (a) From NED0 - 21707, (U) - Unirradiated, (I) - Irradiated I m a r r a L L s - c o t u ra m u s
l l 70 6.5 Hardness The Rockwell B hardness of five irradiated base metal and five irradiated weld metal specimens were measured. The hardness values obtained are given in Table 15. Also shown are the data obtained earlier on unirradiated base and weld metal specimens. Given the error band of about + 1.0 unit, the hardness of the base metal samples is unchanged, while that for the weld metal may have decreased slightly. I I
~
i l iI
\
I BATTELLE -COLUMBUS
. , _ - . - _ . - - - . . - . _ . _ . _ . . _ _ _ _ _ _ _ . _ ~ _ _ _ . _ _ _ . . . _ _ _ . , . . . . . . _ . . _ . _ - _ - . _ _ _ _ _ _ , .-
71 I l TABLE 15. ROCKWELL HARDNESS TEST RESULTS FOR VERMONT YANKEE BASE AND WELD METAL SPECIMENS l I Specimen Material Rockwell B Hardness Average No. Type 1 2 3 4 5 Hardness (a) Steel 91.2 91.5 91.7 91.5 91.5 91.5 + 0.2 JB4 Base (U) 91.2 91.5 90.6 92.2 91.1 91.3 + 0.6 I JC1 JD2 Base (U) Base (U) 92.0 92.0 91.9 91.0 91.5 92.7 91.7 92.6 91.7 92.1 91.8 T 0.2 92.310.4 91.8 91.9 92.5 92.0 + 0.2 I JBB JCA JBD Base (I) Base (I) Base (I) 91.8 92.5 92.6 92.0 92.0 92.2 92.5 92.5 92.5 92.4 91.1 92.1 92.1 7 0.6 92.310.2 JE6 Weld (U) 92.5 93.0 91.9 91.0 92.3 92.1 + 0.8 JJ2 Weld (U) 92.5 93.0 91.9 91.0 92.3 92.1 T 0.8 JK1 Weld (U) 93.3 93.2 93.4 92.0 92.2 92.810.7 JJB Weld (I) 87.9 87.4 88.0 88.2 88.1 87.9 1 0.3 i JJT Weld (I) 90.5 89.9 91.3 90.9 91.2 90.8 + 0.6 JJM Weld (I) 89.9 88.4 89.3 87.9 90.1 89.110.9 l (a) Steel 91.8 91.8 91.7 91.8 92.2 91.9 1 0.2 I (a) Rockwell B Standard Test Block of hardness 91.9 + 1.0. - (u) = Unirradiated, (I) = Irradiated. I I I l BATTELLE -COLUMBUS
72
7.0 CONCLUSION
S I Evaluation of the fast neutron dosimetry, chemical analysis, and mechanical property test (Charpy V-notch, tensile and hardness) results for specimens from the Vermont Yankee Nuclear Generating Plant surveillance I capsule led to the following conclusions: I Neutron Dosimetry I The Vermont Yankee capsule and surveillance specimens o at the 30-degree azimuthal location received a fast 16 2 neutron fluence (E > 0.1 MeV) of 4.3 x 10 n/cm as a result of operation from initial startup to March 1983 (7.54 EFPY). o The Vermont Yankee pressure vessel azimuthal fluence (or flux) varied by as much as a factor of 2. The maximum fast neutron exposure occurred at about the I 0-degree azimuthal position and the lead factor was 0.83 for the pressure vessel inside surface, 1.13 for I the 1/4 T, and 2.89 for the 3/4 T positions. o The maximum fast neutron fluence (E > 1.0 MeV) at the 16 2 pressure vessel 1/4 T position was 3.8 x 10 n/cm as a result of operation from initial startup to March 1983 (7.54 EFPY).
,, o _ Extrapolating the present data to the end of life
' (E0L) of 32 equivalent full power years (EFPY), the maximum calculated E0L fast neutron fluence (E > 1.0 MeV) at the pressure vessel 1/4 T position would be 2 1.61 x 10 n/cm . If a 20 percent accuracy is 17 assumed, the upper bound of the maximum E0L fast neutron fluence (E > 1.0 MeV) at the pressure vessel I7 2 1/4 T position would be 1.9 x 10 n/cm , s ar v s L L s - c o Lu m m u s
s 73 I e The EOL project'ed maximum fast neutron fluence 17 2
*(E > 1.0 MeV) of 2.2 x 10 n/cm at the pressure vessel surface agrees well with the value of between I 2.0 and 2.9 x 10 17 n/cm2 predicted by the Southwest Research Institute.
I Charpy e After a fast neutron fluence (E > 1.0 MeV) of 4.3 x 16 n/cm2 , the irradiated Charpy V-notch specimens 10 l from the Vermont Yankee 30-degree surveillance cap-sule indicate a base metal upper shelf energy of 128 ft-lb, a weld metal upper shelf energy of 122 ft-lb, and a HAZ metal upper shelf energy of 117 ft-lb. These values were sightly higher than those obtained I with the unirradiated baseline materials, except for the base metal which dropped 20 ft-lb. However, these values are still well above the minimum allow- ) able upper shelf energy of 50 ft-lb specified in l 10 CFR 50 Appendix G. Tensile I e All tensile test specimens exhibited ductile failures as evidenced by the cup-and-cone type fracture shape. The tensile properties were essentially the same as those obtained for the unirradiated baseline I , materials. I I EATTELLE -COLUMBUS
74 Chemistry I o The copper, nickel, and phosphorus content obtained at BCL for both unirradiated baseline and irradiated specimens compare well (within about 15 percent) I to the content reported in NE00-21708 except for the copper content in the weld metal and the phosphorus in some of the base and weld metal specimens. o AcomparisonoftheVermontYankeecopper(Ou), nickel (Ni), and phosphorus (P) content to other BWR reactor pressure vessel base and weld metals reported in NED0-21708 shows: (1) The Vermont Yankee Cu content is the lowest for I both base and weld metals, (2) The Vermont Yankee Ni content is the highest for weld metal and in the mid range for the base metal, (3) The Vermont Yankee P content is the lowest for the weld metal and about in the mid range for the base metal o Based on copper content, the base metal is the I limitirg material and, using the NRC Regulatory Guide 1.99, the projected shift in reference nil-ductility 17 transition temperature for a fluence of 5 x 10 i n/cm 2 will be relatively low at less than 100 F. l I Hardness I o The hardness of base and weld metal samples were essentially unchanged as a result of the exposure. I I "^""7"--""
I 75
8.0 REFERENCES
- 1. Reuther, T. C. and Swilsky, K. M., "The Effects of Neutron Irradiation on the Toughness and Ductility of Steels", in Proceedings of Toward Improved Ductility and Toughness Symposium, published by Iron and Steel Institute of Japan (October, 1971), pp 289-319.
- 2. Steele, L. E., " Major Factors Affecting Neutron Irradiation Embrittlement I of Pressure-Vessel Steels and Weldments", NRL Report 7176 (October 30, 1970).
- 3. Berggren, R. G., " Critical Factors in the Interpretation of Radiation -
I Effects on the Mechanical Properties of Structural Metals", Welding Research Council Bulletin, 8_7, 7 1 (1963). l 4. Hawthorne, J. R., " Radiation Effects Information Generated on the ASTM Reference Correlation-Monitor Steels", American Society for Testing and Materials Data Series Publication DS54 (1974).
- 5. Steele, L. E. and Serpan, C. Z., " Neutron Embrittlement of Pressure Vessel Steels - A Brief Review", Ar.alysis of Reactor Vessel Radiation Effects Surveillance Programs, American Society for Testing and Materials I Special Technical Publication 481 (1969(, pp 47-102.
- 6. Integrity of Reactor Vessels for Light-Water Power Reactors, Report by
, the USAEC Advisory Comittee on Reactor Safeguards (January,1974).
- 7. Higgins, J. P. and Brandt, F. A., " Mechanical Property Surveillance of I General Electric BWR Vessels", General Electric Report NED0-10115 (July, 1969).
)3 8. " Standard Practice for Conducting Surveillance Tests for Light-Water g Cooled Nuclear Power Reactor Vessels", ASTM Designation E185-82, Annual Book of ASTM Standards, Part 45 (1982), pp 888-896. ( 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 Energy International Symposium on Application of Reliability Technology to Nuclear Power Plants (Reliability Problems of Reactor Pressure Components) in Vienna, Austria, and published in the Proceedings of that Conference.
- 10. Proposed Research Program (Proposal ho. 585-K-9445) on " Examination, Testing, and Evaluation of Irradiated Pressure Vessel Surveillance I Specimens from the Vermont Yankee Nuclear Generating Station" to Yankee Atomic Electric Company from Battelle Columbus Laboratories, October 27, 1982.
l I !I BATTELLE -COLUMEUS
I 76 I
- 11. " Standard Methods and Definitions for Mechanical Testing of Steel j Products", ASTM Designation A370-77, Annual Book of ASTM Standards, Part 10 (1982), pp 28-83.
- 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.
I 14. ASME Boiler and Pressure Vessel Code, Section III, Subsection NB (Class 1 Components) for Nuclear Power Plant Components, Division 1, NB-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. " Modified Surveillance Program For General Electric BWR Pressure Vessel Steels", General Electric Report APED-5490, May
- 17. Private Consnunications, F. J. Burger and K. R. Willens of Yankee Atomic Electric Company to L. M. Lowry of Battelle's Columbus Laboratories, September 20, 1983.
- 18. Evaluated Reference Cross Section Library by R. L. Simons and W. N.
McElroy, BNWL-1312, May, 1970, Battelle Memorial Institute, Pacific I Northwest Laboratories, Richland, Washington 99352.
- 19. DETAN 81: Computer Code for Calculating Detector Responses in Reactor I Neutron Spectra, C. Esenhauer, National Bureau of Standards, Washington D.C.
- 20. RSIC Computer Code Collection, DOT 4.3 One- and -Two Dimensional I Transport Code System, Radiation Shielding Information Center, Oak Ridge National Laboratory, Oak Ridge, Tennessee, November 17, 1975.
- 21. BUGLE 80 Coupled 47 Neutron, 20 Gamma-Ray, P3 Cross Section Library for LWR Shielding Calculations, RSIC Library DLC-75 I 22. Standard Methods for " Notched Bar Impact Testing of Metallic Materials",
ASTM Designation E23-82, Book of ASTM Standards, Part 10 (1982), pp 277-300.
- 23. Perrin, J. S., Fronrn, E. O., 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 l
I . Nuclear Society (1977).
" Standard Methods of Tension Testing of Metallic Materials", ASTM Desig-24.
nation E8-81, Annual Book of ASTM Standards, Part 10 (1982), pp 197-217. II . . . . . . - _ . .
I 77
- 25. " Standard Recommended Practice for Elevated Temperature Tension Tests of I Metallic Materials", ASTM Designation E21-79, Annual ASTM Book of Stand-ards, Part 10 (1982), pp 267-276.
- 26. The relative power data for the Vermont Yankee core were supplied via a I personal communication from F. J. Berger of Vermont Yankee Nuclear Power Corporation to Mr. Larry M. Lowry of Batte11e's Columbus Laboratories, dated September 20, 1983.
I 27. " Standard Method for Measuring Neutron Flux, Fluence, and Spectra by Radioactivation Techniques", ASTM Designation E261-77, Annual Book of ASTM Standards, Part 45 (1982), pp 930-941.
- 28. " Standard Method for Determining Fast-Neutron Flux Density by Radioacti-vation of Iron", ASTM Designation E263-82, Annual Book of ASTM Standards, I Part 45 91982), pp 951-956.
- 29. " Standard Guide for Application of Neutron Transport Methods for Reactor l Vessel Surveillance", ASTM Designation E482-82, Annual Book of ASTM Standards, Part 45 (1982), pp 1088-1092.
I 30. " Standard Method for Calibration of Germanium Detectors for Measurement of Gama-Ray Emission of Radionuclides", ASTM Designation E522-78, Annual Book of ASTM Standards, Part 45 (1982), pp 1139-1144.
- 31. " 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), pp 1145-1152.
I 32. Lowry, L. M. and Landow, M. P., " Testing of Unirradiated Pressure Vessel Surveillance Baseline Specimens for the Vermont Yankee Nuclear Generating l I Station", Battelle Columbus Laboratories Report, BCL-585-84-1, March 21, 1984. l I l I I tI ....m.-._..
I I I : I , I I I I I APPENDIX A INSTRUMENTED CHARPY EXAMINATION
)
.1 I I I - ,
)
I I I .....m.- _ ...
i l APPENDIX A INSTRUMENTED CHARPY EXAMINATION I INTRODUCTION I The radiation-induced embrittlement of the pressure vessel of a . comercial nuclear reactor is monitored b'y evaluation of Charpy V-notch impact specimens in surveillance capsules. In a conventional Charpy V-notch impact test, the information obtained for each specimen includes the absorbed energy, the lateral expansion, and the fracture appearance. Curves of energy versus , temperature and lateral expansion versus temperature can be drawn for a series I of specimens of a given irradiated material tested over a range of tempera-ture. These curves, when compared to similar curves for the unirradiated material, show the shift in behavior due to irradiation. Information in addition to the energy absorbed can be determined I from a Charpy V-notch impact 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). I The additional information obtained from the instrumented Charpy test includes the general yield load (PGY) (plastic yielding across the entire
- cross section of the Charpy specimen), the maximum load (Pmax), and the crack arrest load. In addition, if brittle fracture occurs, the brittle fracture load (PF), and the time to brittle fracture can be obtained (see Figure A-1).
The area under the load-time curve corresponds to the total energy absorbed, which is the only data obtained in a normal uninstrumented Charpy test. The instrumented test, however, allows separation of the energy abosrbed into (1) the energy required for crack initiation (approximated by the premaximum load energy), (2) the energy required for ductile tearing (postmaximum load BATTELLE -COLUMMUS
l A-2 I . I i- General Yield Land, Pay M 5 aximum Leed,Pmex Brittle Fracture Loed, Pp I , Crack Arrest Loed I ! .=
}
Pre "Meximum Loed" Energy N
= Time to Brittle Fracture Time I
Post "Wemimum Losd" Energy Post Brittle Fracture Energy I I FIGURE A-1. AN IDEALIZED LOAD-TIME HISTORY FOR A CHARPY IMPACT TEST I-I I
A-3 ) energy), and (3) the energ'y associated with shear lip formation (postbrittle I fractureenergy),asshowninFigureA-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 information obtained by instrumenting the Charpy test (4). This information enhances the l value of the relatively small Charpy specimens to reactor vessel surveillance programs. These procedures have received the endorsement of the technical comunity(5), The instrumented Charpy test also gives the information shown in Figure A-1 as a function of temperature, as shown by the example in I Figure A-2. Various investigators (5-8) have developed theories that permit a detailed analysis of the load-temperature diagram. This diagram can be I 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 l fracture occurs upon general yielding. Extended discussions of these fracture parameters can be found in the references indicated above. I EXPERIMENTAL PROCEDURES I The general procedures for the instrumented Charpy test are the same as those for the conventional impact test, and are described in the main text I 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 l 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 lI lI .....m. .. . .
I A-4 I I ' I : I N'
'N
\ Pmax I -
I p Pp ? Pay
} ' I Region 1 Region 2 Rat i on 3 Region 4 Test Temperature I
I I I FIGURE A-2. GRAPHICAL ANALYSIS OF CHARPY IMPACT DATA I I .. ..m..-.. .....
I A-5 I - I < m, f F V o.a e l m
.- (/
and I Amplifier I I Shunt Triggering l Device W Resistance I
. . . , =
g l I I . FIGURL A-3. DIAGRAM OF INSTRUMENTATION ASSOCIATED WITH INSTRUMENTED CHARPY EXAMINATION m AT T a L L s - c o LU M a u s
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 l light beam device at the correct time to capture the amplifier output signal (3,4). I RESULTS AND DISCUSSIONS Specimens of three materials were tested. These materials were 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 1 cad (Psy),themaximumload(Pmax),thefast(brittle)fractureload(P),andthe F arrest load. The load-temperature curves obtained for the three mate-ials are shown in Figures A-8 through A-ll. e I NATTCL.E -COLUMMUB
m m m m m m m m m TABLE A-1. INSTRUMENTED CHARPY IMPACT RESULTS.FOR THE IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE (The energy values listed are obtained from the impact machine dial.) Specimen Test Impact Energy, General Yield Maximum Load Fast Fracture Arrest Load, O Identification Temperature, F ft-lb Load Pgy, Ib Pmax, lb Load, Ib lb j JB1 0 12.5 3072 3382 3380 240 JBK 10 28.0 3012 3946 3946 46 [ JBT 20 17.5 2960 3432 3386 4048 168 78
- JB3 20 32.0 2912 4050 [
n JCC 40 35.0 2908 4056 4054 100 r J01 50 50.5 2850 4096 4086 216 60 54.0 2716 4084 4048 496 h JBB O JBJ 80 76.0 2800 4076 3916 1630 0 JB0 120 92.0 2494 4098 3520 1882 , JCA 160 124.0 2540 3924 N/A N/A JDJ 240 127.0 2352 , 3762 N/A N/A JC5 320 128.0 2443 3780 N/A N/A t i
M M M M M M M TABLE A-2. INSTRUMENTED CHARPY IMPACT RESULTS FOR THE 1RRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 3f.'-DEGREE SURVEILLANCE CAPSULE (The energy values listed are obtained from the impact machine dial.) Specimen Test Impact Energy, General Yield Maximum Load Fast Fracture Arrest Load, Identification Temperature, F ft-lb Load PGY, lb Pmax, lb Load, Ib lb '$ JE5 -80 28.0 3376 4094 4092 54 l j JKP -40 29.0 3280 4036 4026 444 r JEU -30 44.0 3470 3930 3826 438 l 0 JJL -20 49.0 3176 4006 3872 544
' JKM 0 30.0 3136 3984 3982 702 >
o JJT 0 55.5 3058 3914 3736 1136 k c JJ7 19 67.0 3090 4006 3740 1458 3 JJB 40 68.5 2956 3862 3586 1798 , o c JKE 80 99.0 2914 3924 3114 1982 JEC 160 120.5 2652 3676 N/A N/A ) JJ3 240 121.0 2438 3510 N/A N/A j JJM 320 114.5 2386 3420 N/A N/A i I i i 1
m m m M M m m m m m m m M M M M M TABLE A-3. INSTRUMENTED CHARPY IMPACT RESULTS FOR THE IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE (The energy values listed are obtained from the impact machine dial.) Specimen Test Impact Energy, General Yield Maximum Load Fast Fracture Arrest Load, Identification Temperature, F ft-lb Load Pgy, Ib Pmax, Ib Load, Ib lb g
-80 11.5 3374 3788 3780 122 JPA
-40 23.0 3276 4006 3990 42 o JP3
-20 63.5 3174 4182 4082 1976 E JL7
-20 12.5 3254 3468 3454 602 JLT JP6 0 15.0 3184 3576 3564 616 $
D 0 45.5 3132 4070 3996 1468 JP2 c 20 40.5 3164 3926 3868 1376 JLD f C JP8 40 70.5 3048 4030 3832 3938 3744 2224 2596 JP4 80 56.5 3090 JM6 160 105.5 2804 4008 N/A N/A JPC 240 116.0 2836 3900 N/A N/A JMD 320 112.5 2644 3622 N/A N/A
A-10 5000 l l l l l l l SPECIMEN NO. : JB1 TEST TEMPERATURE (F) : g 4000-DIAL ENERGY, (FT-LBS) 12.5 G -- m 3000-GENERAL YIELD LOAD (LB) : .3072 d MAXIMUM LOAD (LB) : 3382 Q 2000--{ I FAST FRACTURE LOAD (LB) : 3380 0 ARREST LOAD (LB) : 240 1000- i 0 ^T ~ l ^ " , l 8 500 1000 1500 2000 TIME (MICRO-SECONOS) 5000 l l l l l l l SPECIMEN NO. : JBK TEST TEMPERATURE (F) : ig 4000- - DIAL ENERGY, (FT-LBS) : 2B G I GENERAL YIELD LOAD (LB) : MAXIMUM LOAD (LB) : 3012 3948 m 3000-d Q 2000- -- FAST FRACTURE LOAD CLB) : 3948 3 ARREST LOAD (LB) : 48 1000- i ' O l - l l l 2 500 1000 1520 2020 TIME CHICRO-SECONOS) I 5000 l l l l l l l SPECIMEN NO. : JBT TEST TEMPERATURE (F) : 20 4000 - - DIAL ENERGY, (FT-LBS) : 17.5 g3000- r/ - GENERAL YIELD LOAD (LB) : 2960 d MAXIMUM LOAD (LB) : 3432 Q 2000- - i l FAST FRACTURE LOAD (LB) 3386 O ARREST LDAD (LB) : 158 1000-O 1 l l 0 800 1600 2400 3220 r TIME (MICRO-SECONOS) FIGURE A-4. INSTRUMENTED CHARPY IMPACT DATA FOR IRRADIATED BASE METAL (LONGITUDINAL) SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE l, SURVEILLANCE CAPSULE lI - - - EATTELLE -COLUMMUS
I l A-11 ) 5000 l l l l l l l SPECIMEN NO. e JB3 TEST TEMPERATURE (F) : 2g 4222 - - 32 G I DIAL ENERGY, (FT-LBS) : m 3ggg. . .. GENERAL YIELD LOAD (LB) : 2912 d MAXIMUM LDAD (LB) : 4252 @ 2222- f -- FAST FRACTURE LOAD (LB) : 4248 O ARREST LOAD (LB) e _78 1000-d 2 2 500 1022 1522 2222 TIME CHICRO-SECONOS) 5222 l l l l ! l l SPECIMEN NO. : JCC TEST TEMPERATURE,(F) : 42 4888 " - DIAL ENERGY, (FT-LBS) : 35 G I m 3222-GENERAL YIELD LOAD (LB) 2928 d MAXIMUM LOAD (LB) 4256 @ 2222- -- FAST FRACTURE LOAD CLB) : 4254 3 ARREST LOAD (LB) e 122 1222- - 2 l ~ ; - ^'; l l 2 B22 1622 2422 3223 TIMC (MICRO-SECONOS) I 5222 l l l l l l l SPECIMEN NO. JD1 TEST TEMPERATURE (F) : 52 4888 " " DIAL ENERGY, (FT-LBS) e 59.5 g "
~
GENERAL YIELD LOAD (LB) 2852 d MAXIMUM LOAD (LB) : 4096 2222-FAST FRACTURE LOAD (LB) : 4286 J 1222-ARREST LOAD (LB) e 216
. . m . .
2 2 800 1822 2422 3222 TIME (MICRO-SECONOS) I FIGURE A-4. (Continued) m a v v a t. t. s - c o t u m m u s
A-12 5928 l l l l l l l SPECIMEN ND. JBB . TEST TEMPERATURE (F) : 62 4888 "
- DIAL ENERGY, (FT-LBS) e 54 g '
GENERAL YIELD LDAD CLB) s 2716 d . MAXIMUM LDAD CLB) 4984 Q 2999- - FAST FRACTURE LDAD (LB) e 4848 : ARREST LDAD CLB) 496 1998- 1
. l l l .
=
m . 5 898 1890 2490 3220 I TIME (MICRD-SECONDS) SPECIMEN ND. JBJ TEST TEMPERATURE (F) 88 4888 " " DIAL ENERGY, (FT-LBS) 76 g " " GENERAL YIELD LDAD (LB) 2890 d MAXIMUM LDAD (LB) 4276 I Q 2998- -- FAST FRACTURE LDAD (LB) e 3916 O ARREST LDAD CLB) e 1838 1990- -
, l l l l <
G 1998 2998 3900 4920 TIME (MICRD-SECONDS) 5998 l l l l l l l SPECIMEN ND. s JBD TEST TEMPERATURE (F) 122 4888 " " DIAL ENERGY, (FT-LBS) e 92 g I , GENERAL YIELD LDAD CLB) e 2494 4848 d MAXIMUM LDAD (LB) Q 2898-FAST FRACTURE LDAD CLB) : 3529 3 ARREST LDAD (LB) e 1882 1988- -- 8 l l ; , l l l 9 2998 4998 6998 8000 TIME (MICRD-SECONDS) i FIGURE A-4. (Continued) I BATTELLE == C O L U M B U S
A-13 5800 l l l l l l l I SPECIMEN ND. s JCA TEST TEMPERATURE (F) e 168 4888 " DIAL ENERGY, CFT-LBS) 124 g " GENERAL YIELD LDAD CLB) e 2549 d MAXIMUM LDAD CLB) e 3924 -- h2999-FAST FRACTURE LDAD CLB) : N/A J ARREST LDAD CLB) N/A 1888-I . a 2ess 4ses essa sesa TIME (NICRD-SECONDS) 5999 l l l l l l l SPECIMEN ND. JDJ 480s TEST TEMPERATURE (F) e 24g DIAL ENERGY, (FT-LBS) e 127 g " GENERAL YIELD LDAD CLB) : 2362 d
- MAXIMUM LDAD CLB) e 3762 Q 2982- --
FAST FRACTURE LDAD CLB) : N/A 3 ARREST LDAD (LB) e N/A 1998-s : : : : : : : 9 2999 4000 Seas 8092 TIME (MICRD-SECONDS) 5800 l l l l l l l I SPECIMEN ND. e JC5 TEST TEMPERATURE (F) e 329 4888" " DIAL ENERGY, (FT-L9S) e 128 g " GENERAL YIELD LDAD CLB) e 2348 d MAXIMUM LDAD CLB) e 3789 2898- -- FAST FRACTURE LDAD CLB) : N/A ARREST LDAD (LB) : N/A 1999-a : : l l l : l s 2ses 4ess sees sees TIME (MICRD-SECDHDS) I FIGURE A-4. (Concluded) MATTELLE == C O L U M M u s
A-14 5890 l l l l l l t I SPECIMEN ND. TEST TEMPERAT'JRE '.F) JE5
-89 4888 "
I l DIAL EFERGY, FT-LBS) : 28 g ) GENERAL YIELD LDAD (LB) : 3376 d 4894 I MAXIMUM LDAD CLB) : -- Q 2999 - I FAST FRACTURE LDAD (LB) e 4992 3 ARREST LDAD (LB) : 54 1500- i
- k. . .
8 . . . . . . S 588 1890 1586 2999 TIME (MICRD-SECDNDS) 5800 l l l l l l l SPECIMEN ND. JKP TEST TEMPERATURE &) e -48 4888 - DIAL ENERGY, FT-LBS) : 29 g I GENERAL YIELD LDAD CLB) e 3288 4936 d MAXIMUM LDAD (LB) : Q 2998- - FAST FRACTURE LDAD (LB) s 4826 3 ARREST LDAD (LB) e 444 1998-1
. r. . , .
9 . . . . . . . 9 588 1999 1590 2222 TIME (MICRD-SECONDS) MH l l l l l l l SPECIMEN ND. s JEU TEST TEMPERATURE F) : -38 4888 " ' DIAL ENERGY, GT-LBS) : 44 g " CENERAL YIELD LDAD CLB) 3479 d MAXIMUM LDAD (LB) : 3938 -- k2998-- FAST FRACTURE LDAD (LB) : 3826 3 ARREST LDAD (LB) e 438 1990-f l . l l TIME (NICRD-SECDNDS) l 2... FIGURE A-5. INSTRUMENTED CHARPY IMPACT DATA FOR IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE' SURVEILLANCE CAPSULE NATTELLE -COLUMeus I -
A-15 l l l l l l l I SPECIMEN NO. JJL TEST TEMPERATURE (F) s -22 4888" DIAL ENERGY, (FT-LBS) 49 ' GENERAL YIELD LDAD (LB) : 3176 4806 I MAXIMUM LDAD CLB) : -- Q 2999 - FAST FRACTURE LOAD CLB) s 3672 3 ARREST LOAD (LB) e 544 1890-o a : : : : : 8 598 1998 1589 2998 I 5809 l TIME (MICRO-SECONOS) l l l l l l SPECIMEN NO. : JKM - TEST TEMPERATURE (F) a 9 4888 - DIAL ENERGY, (FT-LBS) e 38 G " GENERAL YIELD LOAD (LB) 3136 h MAXIMUM LOAD CLB) : 3984 Q 2999- - FAST FRACTURE LOAD (LB) e 3982 3 ARREST LOAD CLB) : 722 1999-9 9 : : . , l l l 9 598 1999 1589 2200 TIME (MICRO-SECONDS) 5890 l l l l l l l l l SPECIMEN NO. e JJT " 4888 " l TEST TEMPERATURE (F) : 8 DIAL ENERGY, (FT-LBS) e 55.5 GENERAL YIELD LDAD (LB) e 3858 MAXIMUM LDAD (LB) : 3914 Q 2898- - FAST FRACTURE LOAD (LB) 3736 3 ARREST LDAD (LB) a 1136 1990- i l l s s See 1sse TIME (MICRO-SECONDS)
- :W 15ee asse I FIGURE A-5. (Continued)
MATTNLLE -COLUMEUs
- . . - . - ~ . - - . - . - - . - . - - , - - - - . - , - - . . . . - - - . . - . . . - - . - - - - . - - . - - - . - -
E A-16 580s l l l l l I l l l SPECIMEN NO. JJ7 19 48E8 TEST TEMPERATURE (F) e
^
DIAL ENERGY, (FT-LBS) : 87 g " GENERAL YIELD LDAD (LB) 3898 d MAXIMUM LOAD CLB) : 4896 Q 2890- - FAST FRACTURE LOAD (LB) 3748 a ARREST LOAD G.9) : 1458 1998-e l l l , -!' , l 8 ees less 24ss 3222 TIME (MICRO-SECONDS) 58es l l l l l l -! SPECIMEN NO. JJB 43 4808 - TEST TEMPERATURE (F) DIAL ENEntGY, CFT-L.BS) : 68.5 G I. m aggg.. .. GENERAL YIELD LOAD CLB) : 2956 d MAXIMUM LDAD CLB) : 3862 Q 2999-FAST FRACTURE LOAD CLB) : 3586 3 ARREST LOAD (LB) : 1798 1998-I S 9 l 809 l l 1688 l 2482 l 3220 TIME (MICRO-SECONDS)
. l l l l l l l .
SPECIMEN NO. JKE 88 4888 " TEST TEMPERATURE (F) DIAL ENERGY, CFT-LBS) : 99 g I GENERAL YIELD LOAD CLE) 2914 d MAXIMtM LOAD (LB) 3924 Q 2989-FAST FRACTURE LDAD CLB) 3114 3 ARREST LOAD CLB) : 1992 1999-s l l l l l l ; -- 9 1998 2998 3898 4288 TIME (MICRO-SECONDS) I FIGURE A-5. (Continued) I BATTELLE -COLUMBUE
I A-17 sees l l l l l l l SPECIMEN NO. : JEC TEST TEMPERATURE 7) : les 4888" DIAL ENERGY, W T-LBS) 129.5 " GENERAL YIELD LDAD CLB) 2652 MAXIMUM LDAD CLB) s 3676 @ 2999- - FAST FRACTURE LDAD CLB) e N/A 3 ARREST LDAD CLB) : N/A 1998-I . 9 1898 2998 3099 l l 4980 TIME (MICRO-SECONDS) 5898 l l l l l l l SPECIMEN NO. : JJ3 I TEST TEMPERATURE (F) : 248 DIAL ENERGY, WT-LBS) : 121 G 4888
- I e 3ggg- .
GENERAL YIELD LDAD CLB) : 2438 d MAXIMUM LDAD CLB) : 3518 Q 2999- -- FAST FRACTURE LDAD CLB) : N/A O ARREST LDAD (LB) : N/A 1999- -- 8 : : . : 'l l f 9 2998 4 ass 6809 8000 TIME (MICRO-SECONDS)
= 5888 l l l l l l l SPECIMEN NO. . JJM TEST TEMPERA *URE (F) : 329 4888 " "
DIAL ENERGY, (FT-LBS) 114.5 i gggg. . -- GENERAL YIELD LDAD CLB) : 2386 MAXIMUM LDAD CLB) s 3428 2999- - -- FAST FRACTURE LDAD CLB) N/A 8 ARREST LDAD CLB) : N/A 1998- " I e : : : : : : : a 1ses 2ssa Seas 4ses TIME (MICRO-SECONDS) I FIGURE A-5. (Concluded) .I l BATTELLE -COLUMBUS
I~ A-18 5889 l l l l l l l I SPECIMEN NO. s JPA TEST TEMPERATURE (F) : -88 4888' ' - DIAL ENERGY, (FT-LBS) : 11.5
)
I GENERAL YIELD LDAD CLB) 3374 MAXIMUM LDAD CLB) 3788 Q 2999- - -- FAST FRACTURE LDAD CLB) 3788 3 1 ARREST LDAD CLB) 122 1998- i 8 l l l l l l 8 588 1999 1588 2200 TIME (MICRD-SECDNDS) I 5898 l l l - l l l l SPECIMEN NO. : JP3 TEST TEMPERATURE (F) -48 4888' ' "" DIAL ENERGY, (FT-LBS) s 23 G a sggg.. .. I GENERAL YIELD LDAD CLB) MAXIMUM LDAD CLB) 3276 4996 d
$ 2808-- --
I FAST FRACTURE LDAD (LB) : ARREST LDAD CLB) 3990 42 J 1998-i - I g d. l 2222 i e ses less 1522 TIME (MICRD-SECDNDS) 5sse l l l l l l SPECIMEN NO. s JL7 TEST TEMPERATURE (F) -2g 4999- - DIAL ENERGY, (FT-LBS) : 63.5 g " GEifRAL YIELD LDAD CLB) s 3174 d . o >AXIMUM LDAD CLB) 4182 2989- -- 4882
}
! FAST FRACTURE LDAD CLB) ARREST LDAD CLB) 1978 1998- -- e ;Pl I l l- l l 9 889 1889 2499 3220 TIME (MICRD-SECDNDS) FIGUREA-6.INSTRUMENTEDCHARPYIMPACTDATAFORIRRdDIATEDHAZMETAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE ! I BATTELLE -COLUMBUS
A-19 580s l l l l l l l SPECIMEN NO. JLT TEST TEMPERATURE (F) : -2g 49f2" - DIAL ENERGY, CFT-LBS) : ^ 12.5 I GENERAL YIELD LDAD CLB) : 3254 g d
'[ "
MAXIMUM LDAD CLB) : 3468 Q 2898-- -- FAST FRACTURE LDAD (LB) : 3454 3 ARREST LDAD CLB) : 682 1998- i - E l l . l l l l s ses 1988 15ss 2ssa TIME (MICRD-SECONDS) sees l l l l l l l SPECIMEN NO. JPS TEST TEMPERATURE (F) 8 4888 " ' DIAL ENERGY, (FT-LBS) : 15 G m 3gg3 .r
/ ..
GENERAL YIELD LDAD CLB) : 3184 d MAXIMUM LDAD CLB) : 3576 Q 2998- -- 1 FAST FRACTURE LDAD CLB) : 3564 3 ARREST LDAD CLB) : 616 1982-} - I 8 9 588 1999 1598 2222 TIME (MICRO-SECONDS) Sees l l l l l l l SPECIMEN NO. JP2 TEST TEMPERATURE (F) 8 4888' ' " DIAL ENERGY, CFT-LBS) : 45.5 G
- m. 3898- - --
GENERAL YIELD LDAD CLB) : 3132 c MAXIMUM LDAD (LB) 4878 Q 2299- -- FAST FRACTURE LDAD CLB) : 3996 I
.J ARREST LDAD CLB) : 1468 1999- 1 --
8 l l . . - c' . l s ses 16es 2488 32ss TIME (MICRO-SECONDS) FIGURE A-6. (Continued) I I BATTELLE -COLUMBUS
I A-20 5888 l l l l l l l SPECIMEN NO. e ?LD TEST TEMPERATURE G) e 29 4888" DIAL ENERGY, WT-LBS) e 48,5 3988- - GENERAL YIELD LDAD CLB) 3164 MAXIMUM LDAD CLB) e 3926 -- h2999-FAST FRACTURE LDAD CLB) 3868 .I ARREST LDAD CLB) e 1376 1998-S l l . -r- ; ; 8 000 1899 2489 3299 TIME (MICRO-SECONDS) 5898 l l l l l l l I SPECIMEN ND. : JPS TEST TEMPERATURE F) : 48 4888" . i DIAL ENERGY, FT-LBS) : 78.5 G a sagg. .. GENERAL YIELD LDAD CLB) : 3848 d I MAXIMUM LDAD CLB) 4838 2988- -- FAST FRACTURE LDAD CLc) 3938 _a
~
ARREST LDAD CLB) : 2224 1989-l 9 l l l l . . l 8 1998 2899 3898 4999 TIME (MICRO-SECONDS) I .388 l l l l l l l SPECIMEN NO. s JP4 TEST TEMPERATURE 7) e 88 4888 " " DIAL ENERGY, WT-LBS) e SS. 5 I GENERAL YIELD LDAD CLB) e MAXIMUM LDAD CLB) 3898 3832 c 2898- - 3744 I I FAST FRACTURE LDAD CLB) : ARREST LDAD CLB) : 2596 1998-S l l l l ; . l 8 888 1699 2488 3229 TIME (MICRD-SECONDS) I FIGURE A-6. (Continued) I IBATTELLE -COLUMBUS
I A-21 I sees l l l l l l l , I SPECIMEN NO. s JM6 TEST TEMPERATURE CF) : 168 4888 * " DIAL ENERGY, CFT-LBS) : 195.5 g " GEPERAL YIELD LDAD CLB) e 2884 d 4888 I MAXIMUM LDAD CLB) Q 2989- -- FAST FRACTURE LOAD CLB) : WA 3 ARREST LOAD CLB) s WA 1888-s : ; ; r l l l s asas does esas sees TIME CMICRD-SECONDS) 5899 l l l l l l l SPECIMEN NO. s JPC TEST TEMPERATURE CF) 248 4888 " "
^
' DIAL ENERGY, CFT-LBS) : 116
$ 3899- -
GENERAL YIELD LDAD J.B) : 2836 d MAXIMUM LDAD CLB) s 3988 Q 2988- -- FAST FRACTURE LOAD CLB) N/A O ARREST LOAD CLB) : WA 1999-s l l l . l l l 8 2003 4988 8899 8998 TIME (MICRO-SECONOS) 5898 l l l l l l l I SPECIMEN NO. s JMD TEST TEMPERATURE CF) : 328 4888" " DIAL ENERGY, CFT-LBS) : 112.5 g ' GENERAL YIELD LOAD CLB) : 2644 d MAXIMUM LOAD CLB) s 3622 Q 2988- -- FAST FRACT1JRE LDAD Q.8) : WA 3 ARREST LDAD CLB) WA 1990-s l l l l l l l
. 2 4 . ..
TIME (MICRO-SECONDS) I FIGURE A-6. (Concluded) J I BATTELLE - C O L U M eB U S
A-22 Leed Displacement Raw Practure Curves Data Remarks Type
! l I a y Pp Brittle fracture Deflection I
Brittle fracture il PGY i Deflection I lll ] d Pay Brittle fracture followed by fracture indicative of shear lip formation Deflection
~
pGY, Stable crack propagation followed by IV , g P max un. table brittle fracture and fracture 3 indicative of shear lip formation Deflection i Pay, Stable crack propagation follewed by V j Pmex fracture indicative of shear lip formation s Deflection stable crack propagation followed by l VI }s PGY, P max Foss deformation l Deflection FIGURE A-8. THE SIX TYPES OF FRACTURES FOR NOTCHED BAR BENDING l 3 15 l m a v i s L L s - c o s. u nn s u s
A-23 I ! 1 I I 5000 M l 4000 y ~% F N M M_ M __
-M -M F
l lt I; M F 3000 =Y-y sy I , S b % Y Y - y Y g F 2000 - F Y General Yield Load M Maximum Load 1000 - F Fast Fracture -
- Arrest Loads l
' ' '. ' P' I I 0 0 50 100 150 Test Temperatura 200 F
250 300 350 I FIGURE A-8. INSTRUMENTED CHARPY LOAD VERSUS TEST TEMPERATURE I FOR IRRADIATED BASE METAL SPECIMENS FROM THE VERMONT YANKEE 30-DEGREE SURVEILLANCE CAPSULE I . I - BATTELLE -COLUMBUS
A-24 l I 5000 I =00 M M a n g tt g . I Y %yfg F M
%g
-M p
Y~ 3000 - S N Y -
-y w
. F 2000 - \
F Y Seneral Yield Load I \ p M Maximus Load F Fast Fracture - Arrest Loads 0 'I 50 100 150 200 250 300 350
-100 -50 0 l
Test Temperature F { I FIGURE A-9. INSTRUMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR IRRADIATED WELD METAL SPECIMENS FROM THE VERMONT YANKEE I 30-DEGREE SURVEILLANCE CAPSULE t SATTELLE -COLUMSUS
A-25 I l l I 5000 I I #M - N M M N M _h M N* l l\ M Y' Y v Y Y 'y T M Y 3000 - p Y F7 I , 5 2000 - F F Y Seneral Yield Load Np l 1000 - M Maximum Load F Fast Fracture - Arrest Loads g 0 150 200 250 300 350
-100 -50 0 50 100 Test Temperature F -
I I FIGURE A-10. INSTRUMENTED CHARPY LOAD VERSUS TEST TEMPERATURE FOR IRRADIATED HAZ METAL SPECIMENS FROM THE VERMONT YANKEE I 30-DEGREE SURVEILLANCE CAPSULE I I .. . .-.. . . .
A-26 APPENDIX A REFERENCES (1) Wullaert, R. A., " Applications of the Instrumented Charpy Impact Test", in Impact Testing of Metals, American Society for Testing and Materials Special Technical Publication 466, p. 148 (1970).
, (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 Impact Testing, American Societ of Testing and Materials Special Technical Publication 563, p. 3 (1973 . (4) Server, W. L., " Impact Three-Point Bend Testing for Notched and Precracked Specimens", Journal of Testing and Evaluation, 6, 1, 29 (1978). (5) Wullaert, R. A., eaitor, "C.S.N.I. Specialist Meeting on Instruit.ented 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, 202, 912 (1964). (7) Tetelman, A. S. and McEvily, A. J., Fracture of Structural Materials, ! John Wiley and Sons, Inc., New York (1967). (8) Kobayashi, T., Takai, K., and Maniwa, H., " Transition Behavior and Evaluation of Fracture Toughness in Charpy Impact Test", Trans. Iron and Steel Institute of Japan,.7_, 115 (1967). I BATTELLE -COLUMEUS l -. - . - _ _ - - - -}}