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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20247L8071998-03-31031 March 1998 Suppl 9 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20203K2741997-12-31031 December 1997 Evaluation of Thermal Fatigue Effects on Sys Requiring Aging Mgt Review for License Renewal for Ccnpp, Final Rept ML20137P7751997-02-28028 February 1997 to Final Rept CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20101H1671996-02-29029 February 1996 Suppl 7 to Final Rept CENPD-279, Annual Rept on C-E ECCS Performance Evaluation Models for 10CFR50.46 ML20203K2991995-12-31031 December 1995 Environ Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel & Piping Fatigue Evaluations, Final Rept ML20094S1841995-11-30030 November 1995 Specific Application of Laser Welded Sleeves for Calvert Cliffs Power Plant Sgs ML20094S1981995-09-30030 September 1995 Bge Calvert Cliffs Station Units 1 & 2 SG Tube Repair Using Leak Tight Sleeves ML20086S9341995-06-30030 June 1995 Reactor Vessel Weld Matl Chemical Composition Variability Study ML20086N2601995-05-31031 May 1995 Nonproprietary SER for Use of Advanced Zirconium-Based Cladding Matls in Calvert Cliffs,Unit 1 Batch R Lead Fuel Assemblies ML20087G1281995-02-28028 February 1995 Suppl 6 to Annual Rept on ABB-CE ECCS Performance Evaluation Models, Dtd Feb 1995 ML20069H9381994-02-28028 February 1994 Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46 ML20082G7001993-11-30030 November 1993 Reactor Vessel Weld Matls for Calvert Cliffs Unit 1 Suppl Surveillance Program ML20058G1841993-11-30030 November 1993 Nonproprietary Reactor Vessel Weld Matls for Calvert Cliffs Unit 1 Suppl Surveillance Program. Rept Issued as 02987-MCC-002 in 1989 as Internal Rept ML20045D9311993-06-30030 June 1993 Analysis of Capsule 97,Calvert Cliffs Nuclear Power Plant, Unit 1,Reactor Vessel Matl Surveillance Program. ML20045B5851993-04-30030 April 1993 Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46. ML20082G7041993-02-28028 February 1993 Chemical Content of Weld Deposits Fabricated Using Heats A8746 & 34B009 ML17227A8291993-02-16016 February 1993 CEOG Program to Evaluate Chemical Content of Weld Deposits Fabricated Using Heats A8746 & 34B009. ML20042H0681990-05-31031 May 1990 Final Rept on Reactor Vessel Pressure-Temp Limits for Calvert Cliffs Unit 1 for 12 Efpys. ML20236A0951989-01-31031 January 1989 Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for Calvert Cliffs Units 1 & 2 ML20151V2841988-01-0101 January 1988 Nonproprietary Extended Statistical Combination of Uncertainties ML20215H6751986-10-17017 October 1986 Nonproprietary Responses to NRC Questions on FATES3B ML20112B4461984-08-31031 August 1984 Evaluation of Interpellet-GAP Formation & Clad Collapse in Modern PWR Fuel-Rods, Final Rept ML20081A2511984-01-31031 January 1984 Rev 2 to Pressurizer Safety Valve Operability Rept ML20080N0841983-09-30030 September 1983 Rev 1 to Pressurizer Safety Valve Operability Rept ML20066C3921982-10-0505 October 1982 Nonproprietary Supplemental Info on FATES3 Stored Energy Conservatism ML20055A0151982-04-30030 April 1982 Nonproprietary Extended Burnup Operation of C-E PWR Fuel ML20054E0601982-04-30030 April 1982 Answers to NRC Questions for Calvert Cliffs Cycle 6 - Set 1. Nonproprietary Version ML20052C1961982-04-23023 April 1982 Nonproprietary Response to NRC Questions of FATES3 & Calvert Cliffs 1 Cycle 6 Reload. ML20050B3621982-03-21021 March 1982 Nonproprietary Partial Response to NRC Questions on CEN-161(B)-P,Improvements to Fuel Evaluation Model. ML20039F8611981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Calvert Cliffs 1 & 2 Reactor Vessels. ML19240B9601981-03-0505 March 1981 Nonproprietary Version of 1981 Calvert Cliffs Unit 2 Refueling Outage:End of Cycle 3 Eddy Current Insp Results on Control Element Assemblies. ML19341B7671980-12-31031 December 1980 Power-Operated Relief Valve Failure Reduction Methods, Final Rept ML20002D9451980-12-22022 December 1980 Nonproprietary Version of End of Cycle 4 Eddy Current Insp Results:Control Element Assemblies (Cea'S) & Guide Tube Sleeves 1980 Calvert Cliffs 1 Refueling Outage. ML19345B1851980-11-19019 November 1980 Nonproprietary Version of Response to Request for Addl Info on Calvert Cliffs 1 Cycle 5 Licensing Submittal. Notarized Affidavit Included ML19338D6831980-09-22022 September 1980 Nonproprietary Version of Description of Modified Assemblies in Calvert Cliffs 1 Cycle 5. ML19338D6791980-08-27027 August 1980 Nonproprietary Version of Descriprion of Prototype Test Program in Calvert Cliffs 1 Cycle 5. ML19210C1111979-11-0808 November 1979 Results of Control Element Assembly Tube Guide Insp Program, Nonproprietary Version ML19209C4581979-10-0808 October 1979 Control Element Assembly Guide Tube Insp Program, Nonproprietary Version ML20002A1111979-05-31031 May 1979 Sleeved Fuel Assembly Insp Results at Calvert Cliffs Unit 1, Nonproprietary Version ML19282A9271979-02-0101 February 1979 Rept of Reconstitutable-B4C Type Control Element Assembly Design for Use in Bg&E Reactor, Nonproprietary 1999-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30
[Table view] |
Text
. -
. . . e l CEN-205(B)-NP RESPONSE TO NRC QUESTIONS ON FATES 3 AND THE CALVERT CLIFFS 1 CYCLE 6 RELOAD April 23,1982 COMBUSTION ENGINEERING, INC.
O 1 8205040487 820427 PDR ADOCK 05000317 P PDR
LEGAL NOTICE This report was prepared as an account of work sponsored by Combustion Engineering, Inc. Neither Combustion Engineering nor any person acting on its behalf:
A. Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or B. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method or process disclosed in this report.
l Question 1 Has the Combustion Engineering ECCS evaluation model (STRIKIN) been modified to account for revisions in the FATES 3 code in areas such as gap conductance?
Response 1 The Combustion Engineering ECCS evaluation model did not require modification to account for revisions in the FATES 3 code. The ECCS model and conputer codes, including the hot rod heatup code STRIKIN-II, remain unchanged from those approved by NRC for compliance with 10CFR50, Appendix K. STRIKIN-II utilizes the FATES 3 burnup dependent characterization of fuel rod conditions (fuel density, pin pressure, fission gas content, plus cold clad and fuel dimensions)asinput. STRIKIN-II then initializes itself based on th,is FATES 3 input and the ECCS analysis assumpti6ns of peak kw/ft and limiting axial power distribution.
a O
e 1-1
'Oucstion.2 .
Qo the pellet volume averaged temperatures and hot rod internal pressures calculated by the FATES 3 code continue to be bounded by those values calculated with STRIKIH if the FATES 3 code is ramped to the some LOCA initial power conditions used by STRIKIN? What are the power distributions used in STRIKIN? What are the fuel (centerline and surface) and cladding (inside and outside) tenperatures corresponding to those results given in Section 8.3 of the Calvert Cliffs Unit 1, Cycle 6 Reload Report? Is this conclusion changed by the instantaneous fission gas release model in FATES 3 or the burnup assumed for the calculation?
Response 2 Pellet volume averaged temperatures and hot rod internal pressures of FATES 3 continue to be bounded with STRIKIN.
STRIKIN-II and FATES 3 were used to calculate fuel temperatures and hot rod internal gas pressures for the same assucptien of burnup, initial pcwer letel, and power distribution for verification. Table 2-1 lists the FATES 3 and STRIKIN-II fuel temperatures and pin pressures predicted at two rod average bu rnups. In each case the same peak power and axial and radial power distributions were assumed. The data shown is not for CC-1, Cycle 6 but for identical fuel with a trapazoid axial power shape set at a peak of 10.46 ku/ft and an axial average of 9.39 kw/ft. The 4500 MWD /MTU data is typical of early in life fuel conditions. This corresponds to fully densified fuel, maximum fuel-clad, gap size and hence the time of maximum stored energy in the fuel.
The 25,500 MWD /MTU data is typical of end of cycle fuel conditions with high pin pressures, fuel-clad contact and relatively low stored energy in the fuel.
For both conditions, a close correspondence between fuel centerline, fuel ,
surface and volume average fuel temperatures is shown. The STRIKIN-II volume I averaged tenperatures are shown to be slightly higher than FATES 3. The pin pressure is transferred directly from FATES 3 to STRIKIN-II. Therefore, there is an exact correspondence of this parameter.
2-1
- The powet dist,ributions used in STRIKIN-Il for E' CS C performance. calculations have four basic components. First, a g:neric normalized axial powir s-distribution is used for all C-E ECCS . calculations having a 1.68 peaking factor at 65% of the core height. This generic axial shape was developed from sensitivity studies documented in CENPD-132-P and reviewed and approved by NRC for conservative application in C-E ECCS performance analyses., Second, the normalized radial distribution of heat generation rate in the fuel pelle: is transferred as input directly from FATES 3. Third, the absolute power generation in STRIKIN-II is defined by selecting a target peak linear heat rate (kw/f t) input specification for the peak power node. Fourth, fractions of total rod power generated in the pellet, clad and coolant are specified. Thes e ,
four components together yiele a complete definition of the hot rod poder distribution.
Table 2-2 lists the actual initial fuel and clad temperatures predicted by STRIKIN-II at 15.5 kw/ft at the two burnups discussed in Section B.3 of the:
Cycle 6 reload report.
STRIKIN-II remains consistent with the fuel parameter predictions of FATES 3 at all burnups and this conclusion is not changed by the instantanacus fisalon gas release model in FATES 3. --
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2-2
l t
.. s TABLE'2-1
. s
- Comparison of FATES 3 and STRIKIN-II Fuel Parameter Predictions s.
Comparison 0 4500 mwd /mtu (Rod Average Burnup):
Code Fuel Centerline Fuel Surface Volume Avg. Pin Pressure Temp (F) Temp (F) Fuel Temp (F) (psia)
FATES 3 2625 1058 1782 1178 STRIKIN-II 2624 - 1071 1793 1178 Comparison 0 25,500 mwd /mtu (Rod Average Burnup):
FATES 3 2275 839 1495 1646
( STRIKIN-II 2280 853 1508 1646 d
2-3
TABLE 2-2 STRIKIN-II Fuel Parameter For Calvert Cliffs Unit I Cycle 6 Burnup_ Fuel Temperature (*F) Clad Temp (F) Pin Pressure Center .
Line Surface Vol Avg. ID OD (osia) 3000 mwd /mtu 3C34 1044 2213 767 663 1251 34000 mwd /mtu 3551 992 2127 766 663 2191 I
e
e
- f 4
2-4 l
Question 3 Please supplement Section 2.4, " Application of fission gas release model to a variable fuel temperature history" in sufficient detail to permit programming of the model in an NRC fuel performance audit code.
Response 3 Combustion Engineering has developed a fission gas release model which uniquely accounts for variable power and temperature history. The new model accounts for gas release from individual regions of a fuel pellet (radial rings) and more properly calculates fission gas release rate based on the current unreleased fission gas inventory in each region. In addition, the mechanism of grain boundary sweeping which accompanies grain growth is recognized and the associated fission gas release modeled. C-E believes thisfeature to be particularly important in modeling fission gas release after a significant power increase. A description of the method by which C-E models the fission gas release equations described in CEN 161(B) is given below and is followed by a detailed example. .
T Q . . . . . .. .. : . _::=. ^ : .. -- - T.::._; ; - --- .__ T3- _ L ; ; ;_-
~~~
These empirically derived curves are described by
. . ~ ~ [~.
I (3-1 )
. whsre (3-la)
(3-lb)
~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - '
l Terms are the same as defined in Section 2.2 of CEN 161(B).
~
- = . .. .:.._..--_..----- - ._ - - ,_. - - - - - - - - - - - - - - . - - - . - . -
Ignoring grain growth for the moment, the fission gas inventory is computed
- ~ ~ -
from Equation 3-1 using specific rules _.. _ . .. . _. __ _ _ . . . . _ . _ __. . _ . . . _ . .
and then computing the release fraction from 1
(3-2) 1 The rules necessary for application to a variable temperature history are:
1.[
M m
~
- 2. _
M emu W.
- 3. _
- 4. __
i l l
l
.mn 3-2
\
l
kf tempar'atures are sufficiently high for a period of tima, grain growth occurs as described by Section 2.2 of CEN-161(B). If grain growth is predicted to
. occur during an increment of history, then an additional decrease in inventory
. (or gas release) is computed __ _ , _ _ _ _ _ _ _ _
as described above. This decrease in inventory is given by (3-3)
Terms are the same as defined by CEN-161(B). Rules applied when grain growth occurs are:
~:~ ~ . . . :~ ~ : . . .
~
.._. _~ . -
' ~ ' ~. ~.~ ..
-- . - . . . . ~ ::.r ~. - .:: _ ~---
~* * ~ - ~ ^ ^ - - - - - ~ * - - - - - ' ' - " ~ ~ ~ ~ ~ ~
2_ _
...q a
T_ - . . . . _ _ . . . . ... - - - - . . . . - . - - - - . _ . . . . .- . . - - -
..~_L~~~__.
~
_- ~_...._'--' '_- .. T .
~" ~~ ~
~
- - . .a An example of cycling between two temperature leve,ls Tj and T2 is given in
~ ~~ '~ ~~
Figure 3-1. - .
=* * * - - * = - - - - -
p.N. . .. .i . .6 .'
r 3-3
The additional increments shown in the figure follow the same pattern.
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Figure 3-1 i
FATES 3 MODELING OF TEMPERATURE CYCLING BELOW TEMPERATURE
. FOR RESTRUCTURING (CONSTANT GRAIN SIZE) m 4
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