ML081900084
| ML081900084 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/15/2005 |
| From: | Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CC-AA-309-1001, Rev 2 OC-05Q-307, Rev 0 | |
| Download: ML081900084 (51) | |
Text
ENCLOSURE 3 "FEEDWATER NOZZLE GREEN'S FUNCTIONS" (FILE NO. OC-05Q-307), REVISION 0
, xel~n5 CC-AA-309-1001 Revision 2 Page 28 of 61 Nuclear ATTACHMENT 1 Design Analysis Cover Sheet Page 1 Design Analysis (Major Revision)
Last Page No. 6 31 (calc.) & A17 {Appx.)
Analysis No.: I SIA # OC-05Q-307 Revision: 2 0
Title:
Feedwater Nozzle Green's Functions ECIECR No.:
05- 00365 Revision:
0 Station(s):
Oyster Creek Component(s): 1 Unit No.:
1 Discipline:
Mechanical Eng.
Descrip. CodelKeyword: 1ý Fatigue Analysis SafetylQA Class:"
Q System Code: 12 422 & 104 Structure: 13 Feedwater Nozzle CONTROLLED DOCUMENT REFERENCES 16 Document No.:
From/To Document No.:
From/To MPR Report # MPR-783 From SIA Report # SIR-88-028 From Calculation # C-1 302-422-E540-046 From Is this Design Analysis Safeguards Information?1 Yes ]
No [
If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? 17 Yes ]
No Z If yes, ATI/AR#:
This Design Analysis SUPERCEDES: 16 in its entirety.
Description of Revision (list affected pages for partials): 19 Initial Issue to OC Records Management, as part of Licensing Renewal Project.
Preparer: 20 See Page 1 b for SIA Sign's Print Name Sign Name Date Method of Review: 21 Detailed Review Z Alternate Calculations (attached) 5 Testing Ii Reviewer: 22 See Page lb for SIA Sign's Print Name Sign Name Date Review Notes: 2 Independent review [
Peer review 5 (For Saternal Analyeas On'y)
External Approver:
- See Page lb for SIA Sign's Print Name Date Exelon Reviewer: 2S Julien Abramovici Print Name nae Date Is a Supplemental Review Required? 26 Yes Z
I yes, complete ttachment 3 Exelon Approver:. 2?
F. Howie Ray Print Name Sign Date
Exelon.
CC-AA-309 Revision 4 Page 16 of 16 Nuclear ATTACHMENT 2 Owners Acceptance Review Checklist for External Design Analysis Page 1 of I DESIGN ANALYSIS NO. SIA # OC-05Q-307 REV: 0 SHEET la of
- 1.
Do assumptions have sufficient rationale?
Are assumptions compatible with the way the plant is operated and with the licensing basis?
- 3.
Do the design inputs have sufficient rationale?
- 4.
Are design inputs correct and reasonable?
Are design inputs compatible with the way the plant is operated and with the licensing basis?
- 6.
Are Engineering Judgments clearly documented and justified?
Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis?
- 8.
Do the results and conclusions satisfy the purpose and objective of the Design Analysis?
Are the results and conclusions compatible with the way the plant is operated and with the licensing basis?
Does the Design Analysis include the applicable design basis documentation?
- 11.
Have any limitations on the use of the results been identified and transmitted to the appropriate organizations?
- 12.
Are there any unverified assumptions?
- 13.
Do all unverified assumptions have a tracking and closure mechanism in place?
- 14.
Have all affected design analyses been documented on the Affected Documents List (ADL) for the associated Configuration Change?
Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments? (If the input sources or
- 15.
analysis methodology are based on an out-of-date methodology or code, additional reconciliation may be required if the site has since committed to a more recent code)
Have vendor supporting technical documents and references (including GE DRFs) been reviewed when necessary? I I
Yes 0]
0]
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0]
No N/A El
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[]
0]
0]
1:1 El EL 0
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Cl El 0
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Li Li 0
Li Li DATE: P110, EXELON REVIEWER: Julien Abramovici
~FILE No.: OC-05Q-307 STRUCTURAL CALCULATION INTEGRITY PACKAGE PROJECT No.: OC-05Q Associates, Inc.
PROJECT NAME: Oyster Creek Neutron Embrittlement and Fatigue License Renewal Activities CLIENT: Exelon Generation Company, LLC CONTRACT NUMBER: 10002039 dated 6/8/2004 CALCULATION TITLE: Feedwater Nozzle Green's Functions Project Mgr.
Preparer(s) &
Document Affected Approval Checker(s)
Revision Pages Revision Description Signature &
Signatures &
Date Date 0
1-31, Initial issue.
G.L. Stevens Eric Jones
- d. A4ti EEJ 07/20/2005 Appendix A 7100zoI*.5 Al -A 17 M. Qin In Computer MQ 07/ 0/2005 Files Page l'of 31 F2001RI
Table of Contents 1.0 OBJECTIVE..............................................................................................
4 2.0 GEOMETRY..............................................................................................
4 3.0 MATERIAL PROPERTIES.............................................................................
4 4.0 APPLIED LOADS........................................................................................
7 4.1 Pressure Load..................................................................................
7 4.2 Thermal Load.................................................................................
11 5.0 THERMAL AND PRESSURE LOAD RESULTS..................................................
14 6.0 ATTACHED PIPING LOADS.........................................................................
22 7.0 PEAK STRESS FACTOR..............................................................................
26
8.0 CONCLUSION
S.........................................................................................
26
9.0 REFERENCES
31 APPENDIX A: COMPUTER INPUT AND OUTPUT FILES...........................................
Al List of Tables Table 1: Feedwater Nozzle Material Properties..............................................................
6 Table 2: Heat Transfer Coefficients for Oyster Creek Feedwater Nozzle................................
12 Table 3: Pressure Results......................................................................................
15 Table 4: Piping Load Calculations............................................................................
25 Table 5: Safe-End Node 1344 Data..........................................................................
27 Table 6: Blend Radius Node 584 Data.......................................................................
28
List of Figures Figure 1: Oyster Creek Unit I Feedwater Finite Element Model.......................................................
5 Figure 2: Element Plot of Applied Cap Load to As-Modeled FW Nozzle.........................................
8 Figure 3: Element Plot of Applied Internal Pressure Load to As-Modeled FW Nozzle.....................
9 Figure 4: Element Plot of Applied Mechanical Boundary Conditions to As-Modeled FW Nozzle...... 10 Figure 5: Thermal Regions of Oyster Creek Feedwater Nozzle
...... 12 Figure 6: Applied Green's Function Temperature Step Change.......................................................
13 Figure 7: Temperature Plot of Steady-State Condition (5507F)........................................................
16 Figure 8: Temperature Plot at Time = 3.1 Seconds...........................................................................
17 Figure 9: Maximum Total Thermal Stress Intensity (Time = 3.1 seconds)...................
18 Figure 10: Maximum Total Pressure Stress Intensity from Applied Pressure Load.........................
19 Figure 11: Safe End Critical Thermal Stress Location, Node 1344................................................
20 Figure 12: Blend Radius Critical Pressure Stress Location, Node 584............................................
21 Figure 13: External Forces and Moments on the Recirculation Outlet Nozzle................................
22 Figure 14: Safe-End Node 1344 Green's Function..........................................................................
29 Figure 15: Blend Radius Node 584 Green's Function.....................................................................
30
1.0 OBJECTIVE The objective of this calculation is to develop Green's Functions (GF) for the feedwater nozzle at Oyster Creek (OC).
To accomplish this task, a temperature step change was applied to a detailed, two-dimensional (2-D) axisymmetric finite element model (FEM) of the feedwater nozzle, exclusive of the thermal sleeve. Bounding stress histories were extracted from two peak stress locations, one each in the blend radius and the safe end regions. These stress histories were then divided by the actual temperature step change applied to develop Green's Functions for each location. The Green's Function methodology is described in Section 3.3.1 of Reference [7]. This Green's Function is input to the FatiguePro software, and is used with actual plant feedwater temperature data to develop "on-line" thermal stress histories for the feedwater nozzle. From these stress histories, fatigue usage is determined and monitored at each feedwater nozzle location.
2.0 GEOMETRY A 2-D axisymmetric finite element model (FEM) was developed using the ANSYS finite element analysis software [2].
The geometry and material properties used in Reference [1] and [4] were utilized in this evaluation. The meshed model is shown in Figure 1. Reference [1] reflects the changes made in geometry due to work done on the nozzles in 1977.
3.0 MATERIAL PROPERTIES The original construction drawing, Reference [4], designates the material for the feedwater nozzle safe-end to be SA-105, Grade I11. The nozzle forging is SA-336 (equivalent to SA-508 Class 2) and the vessel plate material is SA-302 Grade B low alloy steel. The material properties used for the finite element analysis can be found in Table 1. For the FEM analysis, material properties at 3250F were used, because it is the average of the original feedwater nozzle temperature (550°F) and the thermal shock temperature (100*F).
Use of temperature dependent material properties is not appropriate since this is a linear analysis that uses Green's Functions to determine stresses.
The Green's Function integration process requires linear characteristics, so the introduction of temperature dependent non-linearities would lead to inaccuracies and difficulties in the Green's Function integration process. In addition, the product of Ea for low ally steel, which is the most influential parameter for thermal stress analysis, varies by less than 6% between 325°F and the maximum operating temperature of 550*F. This is considered to be
'Note: All material identifiers in this calculation utilize "SA' designations to line up with current-day material specifications. It is recognized that most OC material identifiers originally used "AK designations. For the purposes of this calculation, both identifiers are considered to be identical.
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within the accuracy of this analysis. Considering that the peak stress for many of the significant (controlling) transients occurs at a temperature less than 325T, the use of the Ea product at 325°F is bounding for these severe transients (since Ea is less for low temperatures).
The coefficients of thermal expansion (a) are instantaneous coefficients. They are used instead of mean values because they are more conservative. Also, since temperature dependent coefficients are not used, and the instantaneous coefficient at 325TF is very close to the mean value at 550TF, so the usage of an instantaneous coefficient is appropriate.
I INSY5s 4
x Feedwater Nozzle Finite Element Model Figure 1: Oyster Creek Unit I Feedwater Finite Element Model
Table 1: Feedwater Nozzle Material Properties Material Properties All Steels: Poisson's Ratio 0.3 Density 0.283 Reactor Vessel Plate (SA 302 Gr.B) [6, Material Group D]
T a
E Thermal Conductivity, K Thermal DiffusMty Specific Heat, Cp F
in/i*F psi BTUlhr*ftsF ft 2 hr BTUAb'F 300 7.74E-06 2.80E+07 24.7 0.42 0.12 350 7.88E-06 24.7 0.409 0.123 400 8.01E-06 2.74E+07 24.6 0.398 0.126 326 7.81E-06 2.79E+07 24.7 0.4146 0.1216 Nozzle Forging (SA 336 with Code Case 1236-1) [6, Material Group A]
T a
E Thermal Conductity, K Thermal Diffusivity Specific Heat, Cp F
in/n'F psi BTUAhr'ft'F ft21*r B7VAb*F 300 7.30E-06 2.85E+07 23.9 0.406 0.120 350 7.49E-06 23.Y 0.396 0.122 400 7.66E-06 2.79E+07 23.6 0.385 0.125 326 7.396E-06 '2.84E+07 23.8 0.401 0.121 Safe End (CS-I SA-106 Gr. II) 16, Materiel Group B]
T a
E Thermal Conductivty, K Thermal Diffusivity Specific Heat, Cp F
i/ihn'F psi BTU/hr'fftF ft 2/hr BTU/4b*F 300 7.18E-06 2.81E+07 28.4 0.481 0.1207 350 7.47E-06 28.0 0.464 0.1234 400 2.75E+07 326 7.326E-06 "280E+07 28.2 0.4726 0.1221
4.0 APPLIED LOADS Both pressure and thermal loads will be applied to the finite element model.
4.1 Pressure Load A uniform pressure of 1000 psi was applied along the inside surface of the feedwater nozzle and the reactor vessel wall. A pressure load of 1000 psi was used because it is easily scaled up or down to account for different pressures that occur during transients. In addition, a cap load was applied to the piping at the end of the nozzle to account for the attached piping, which is not modeled. This cap load was calculated as follows:
PCAP
=
.2 i2 where:
P = Pressure = 1000 psi Di= Inner Diameter = 9.375 in Do= Outer Diameter = 11.000 in Therefore, the cap load is 2654.6 psi. The calculated value was given a negative sign in order for it to exert tension on the end of the model. The nodes on the end of the safe-end are coupled in the axial direction (UY) to ensure mutual displacement of the end of the nozzle due to attached piping.
In order to properly model the feedwater nozzle in ANSYS, the analysis was done as a penetration in a sphere and not a cylinder. To make up for this difference in geometry, a conversion factor of 3.2 times the cylinder radius was used to model the sphere (sphere radius equals 341.501").
The ANSYS input file OCFWNGEOM.inp generates the feedwater nozzle geometry and OCFWNPRES.inp performs the internal pressure load case just described. Figures 2, 3, and 4 show the applied axial cap load on the safe end, the applied internal pressure distribution, and the applied symmetric boundary conditions on the vessel wall and coupling on the safe end, respectively.
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EL 8MENTS EURMWNTS PRES-NORM PRES-NORM OCT 5 2004 13:28:18 Figure 2: Element Plot of Applied Cap Load to As-Modeled FW Nozzle v
'117777M" Figure 3: Element Plot of Applied Internal Pressure Load to As-Modeled FW Nozzle Revision 0
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ELENESTS U
OCT 5 2004 13"221t=2 ELENENTI U
OCT 5 2004 13:21:32 EMAEMENTS OCT 5 2004 13:21:32 x
Figure 4: Element Plot of Applied Mechanical Boundary Conditions to As-Modeled FW Nozzle
4.2 Thermal Load Thermal loads are applied to the feedwater nozzle model for a 100% rated flow thermal shock.
The regions were given an initial temperature of 550'F and then the heat transfer coefficients and temperatures were changed to simulate the L00F flow condition.
The total flow rate of the feedwater system is 7.217 Mlb/hr divided into four feedwater nozzles. Thus, the total flow rate divided by four gives a rated flow rate for each feedwater nozzle equal to 1.80425 Mlb/hr, or 3,964 gallons per minute (gpm).
The heat transfer coefficients (HTC) for each of the GFs were determined and obtained from FWN-HT-COEFF.xls. This set of Excel worksheets calculates HTC's with geometry and flow condition input. HTC's were found for regions 1-4 and 6 of Figure 5. Region 5 uses a HTC that is an average of Region 1 and Region 2. The HTC's calculated from this spreadsheet are similar to the ones used in the original FatiguePro calculations [3). The HTC value for region 4 at 100%
flow case is the same as that used in reference (3], because the spreadsheet used in the calculations for other regions does not allow for HTC calculation at the inner wall of a vessel. Figure 5 shows the regions for application of HTC's. Table 2 depicts the HTC's at no flow and full flow conditions.
ELKIWZU4 v-si i
j~I~ -.
7 OC'T 4 2004 15.13:32 Region G E~denll Region 3 BIlend Radius Region 2 Nozzle FolgIng Region5 Tronmon Region I Safe End x
Figure 5: Thermal Regions of Oyster Creek Feedwater Nozzle Table 2: Heat Transfer Coefficients for Oyster Creek Feedwater Nozzle 0% Flow Case Heat Transfer Region Temperature Coefficient OF Btu/hr.f*-OF 1
550.0 205.1 2
550.0 205.1 3
550.0 205.1 4
550.0 205.1 100% Flow Case Heat Transfer Region Temperature Coefficient OF Btu/hr-ft-OF 1
100.0 2108.8 2
325.0 673.9 3
325.0 191.8 4
550,0 1000.0 Revision 0
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Figure 6 depicts the graphical representation of the applied temperature step change to the feedwater nozzle. Thermal Regions 1, 2, 3, and 5 experience the step change. Thermal Region 4 remains at 550'F and Thermal Region 6 remains at 70'F (ambient temperature) during the step change, which occurs on the inner diameter of the feedwater nozzle (i.e., flow path). The thermal response of the shock is analyzed out to 20,000 seconds.
Green's Function Applied Temperature Shock to Regions 1-6 6 0 0.....
'L
& 400 300 Regionl LM m Region 2 CL
-Region 3
- 200-
-x-.
Region 4 a
x Region 5 I-
-Re--Rgion 6 100 p
0
-50 0
50 100 150 200 Time (sec)
Figure 6: Applied Green's Function Temperature Step Change
5.0 THERMAL AND PRESSURE LOAD RESULTS The thermal load described in the previous section was run on the feedwater FEM. The thermal transient input file is OCFWN_THM. The input file used to find the stress due to thermal loading is OCFWNTHSTR.inp.
Fatigue usage in components such as the feedwater nozzle are almost always controlled by limiting stresses caused by the severe "step change" thermal transients specified in the design basis. Since the Green's Function unit input transient is a step change, the peak stress response from this input transient provides a valid way of establishing the limiting point.
The limiting safe end location was chosen as the node with the highest stress intensity due to thermal loading. Figure 7 shows the temperature distribution for steady-state condition at 5501F. Figure 8 shows the temperature distribution at time = 3.1 seconds, which corresponds to the greatest thermal response produced by the applied temperature step change. The highest total stress intensity due to thermal loading occurs at Node 1344 on the inside diameter of the feedwater nozzle safe-end at a time of 3.1 seconds. Figure 9 depicts the location showing a total thermal stress intensity value of 67,246 psi for Node 1344. Node 1344, shown in Figure 11, was therefore selected as the limiting safe end location for analysis.
The limiting blend radius location was chosen based upon the highest total stress intensity due to pressure loading as shown in Figure 10. The input file used to apply the pressure loading is OCFWNPRES.inp. The limiting location is at Node 584 and is depicted in Figure 12.
The stress intensity time history for the limiting safe-end and blend radius locations were extracted using the ANSYS post-processing files XTR BR.POS and XTRSE.POS for the blend radius and safe end locations, respectively. The ANSYS PRESECT command is executed to extract the linearized stress history along a path from the selected location (safe end and blend radius) to a node on the external surface. Figures 11 and 12 show the linearized stress path for the safe end and blend radius, respectively. The post-processing file produces two raw output files, one for the safe-end and one for the blend radius location (contain the membrane plus bending and Total thermal stress histories), SEFLW.out and BRFLW.out. The membrane plus bending (M+B) stresses and total stresses for the Green's Functions were extracted from the raw output files to produce the corresponding 'clean' files SE.cln and BR.cln.
All *.POS, *.OUT, and *.CLN files are located in the computer files.
As the models were run with a 450'F step change in temperature at the safe end and 225°F step change at the blend radius and the Green's Functions are for a 1F step change in temperature, all safe end data values were divided by -450 (AT) and blend radius data values were divided by -450
(AT). The governing Green's Function plots for the feedwater nozzle safe-end and blend radius locations are shown in Figures 14 and 15. The data for the Green's Functions is contained in Excel files OCGreenFCN.XLS, which is located in the computer files.
The pressure stress intensities for the safe-end and blend radius paths were extracted using the ANSYS post-processing files XTRSEPRES.POS and XTRBRPRES.POS for the Safe End and Blend Radius locations, respectively. These files produced SEPRESFLW.OUT for the safe-end and BRPRESFLW.OUT for the blend radius.
Results of the internal pressure load case are for Node 584 (blend radius) with total stress intensity of 56,070 psi (BR PRESFLW.OUT) and for Node 1344 (safe-end) a total stress intensity of 7,767 psi (SE PRESFLW.OUT). The M+B stress intensity at Node 584 and Node 1344 are 53,150 psi and 7,732 psi, respectively. Table 3 shows the final pressure results for the safe-end and blend radius.
Table 3: Pressure Results Membrane plus Total Stress Location Bending Stress Intensity Intensity (psi)
(psi)
Safe End 7,732 7,767 Blend Radius 53,150 56,070
JUL 6 2005 14:21::39 NODAL SOLUTION STEP=X SUB =1 TIME -. 100E-09 TEMPi (AVG) aSYS-0 SMNW-545.158 SMX
-549.794 545.138 546.188 54"1.218.
5484249.
349.279 545.67.1.
546.703 447.134!
540.764 34*.194 NODAL SOLUTION JUL 6 2005 14:21:39 STEP-1 SUB
-1 TIME
. 100E-09 TEMP (AVG)
.159 794 x
J..28
-4~4 4.1
.4.4 4.7 345A58 546.180.
547.218
~~i1~8.24I 549.219 us5il5e.
546A1W
.54"7.218
..546:.240..
- 549.2";4 545.6 73 546.703
$47.734 540.164 549.794 2-D AUisymmetric OC Feedwater Nozzle FEr
.545.1.58 54".186.
54T;218.
- '5*WG.2,41 549.219 345.673 546. 703 547.734 568.764 549.794 1 for Green' F
- unctions Figure 7: Temperature Plot of Steady-State Condition (5500F)
ANSYS M~L 6 2005 14 :23 ý01 NODAL SOLUTION TEMP (AVG)
SMN =246.753 St4X =~549.812.
246.71 31.
'l 446 44S.M9.
, 14.JA9 280.4214 347.1713 41-5.119 482.446 549.01Z 3
AN~
N NODAL SOLUT ION TIME=3.1 TEMP (AV(
RSYS=0 SMN =246.753 WM&i-=549. 91-2 J.UL 6 200.5 14:23:01 G*
x x
244.753.
314.1
- 341.446 448~72Z
.516.159 246.753 314.1 381.444 410.703-516.139 280.426 34.7.73 415.119 482.466
.549.412 2-D Axis.yuuetric' OC Feedwater Nozzle YEI
,246.753.
- 31.. I 3BI1, 6 44S]8.'793-1-6.139 280.;426 347.713:
415.119 482.45*
549.81.
for Green's Functions Figure 8: Temperature Plot at Time = 3.1 Seconds
NODAL SOLUTJION 5TEP=:302 SUB oil TIME-3. I SINT (AVG) nbC =1.39 SMN =6.2417 SMX, =672-46 NODAL SOLUTION STEP-302 SUB =1 TINE.=3.1 LINT (AVG)
ANS (
JUL 6 2005 14:14:36 SHX -67246 6.247 1494e 29830 44832 59774 X
,6.24.7 149.49 29890 44.832 59774.
7477 22419 Feedwater Nozzie Finite Element Model 37361.
52303 67246 Figure 9: Maximum Total Thermal Stress Intensity (Time = 3.1 seconds)
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NODAL SOLWT~ON 3TZP=-1 MM~ =1 TIMEPI STAT (AVG)
Mac
=.212463 SUN =1595 SW2
=56070 2
NODAL SOLM10I STEP--
StINT (AVO MMC =.212463 514 =1595 8wc =56070 1595 13700 25804 37211 50017 7648 19753 31859 43964 54070 1595 13700 25806 7648 19753 Feedwater Nozzle Finite Element Model 31859 37911 43964 50017 56070 Figure 10: Maximum Total Pressure Stress Intensity from Applied Pressure Load Revision 0
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\\
Node 1344 M3 Figure 11: Safe End Critical Thermal Stress Location, Node 1344 Revision 0
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I ELEMENTS TYPE NUM Node 584 M Figure 12: Blend Radius Critical Pressure Stress Location, Node 584
6.0 ATTACHED PIPING LOADS Along with pressure and thermal effects, the piping stress intensity (stress caused by the attached piping) was determined. These piping forces and moments are determined as shown in Figure 13.
F.
Figure 13: External Forces and Moments on the Recirculation Outlet Nozzle The following formulas are used to determine the maximum stress intensity in the nozzle at the two locations of interest. From engineering statics, the piping loads at the end of the model can be translated to the first and second cut locations using the following equations:
For Cut I:
(M.), =M.-FYL (My), = My + FýLj For Cut II:
(M9 2 =M. -FL 2
(My)2 = My + F1 L2
The total bending moment and shear loads are obtained using the equations below:
For Cut I:
A
= (M.)12 +(Af)12 F.Y = F7r), + (F,),
For Cut II:
M.,
=
(M.)2 ' +(My) 2 F., = ý(F.)j
+ (Fy)2 The distributed loads for a thin-walled cylinder are obtained using the equations below:
N,-Rx F*+--R*
1 [
M21 qN F.+
7rRNL 2RNI To determine the primary stresses, Pm, due to internal pressure and piping loads, the following equations are used.
For Cut 1, using thin-walled equations:
PaN Nz
( P,)z = Pa + N 2 tN t N (P
)O = PaN tN (PM)R = -
tN SiMX 2 1
+(
)Z 9 2
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Note: For this analysis, the pressure load was applied to the ANSYS model and the resulting pressure stresses were taken from ANSYS. Therefore, they were excluded from the above equations.
Because pressure was not considered in this analysis, the equations used for Cut I are valid for Cut II.
where:
L1 The length from the end of the nozzle where the piping loads are applied to the location of interest in the safe end.
L2 The length from the end of the nozzle where the piping loads are applied to the location of interest in the blend radius.
Mxy = The maximum bending moment in the xy plane.
Fr, = The maximum shear force in the xy plane.
N, = The normal force per inch of circumference applied to the end of the nozzle in the z direction.
qN = The shear force per inch of circumference applied to the nozzle.
RN = The mid-wall nozzle radius.
There are four feedwater nozzles in the system (N4A, N4B, N4C, and N4D). The largest reaction forces need to be found and applied for this analysis. It is assumed that nozzles N4A and N4B bound N4C and N4D. Nodes 5 and 140 represent N4A and N4B. The node with greater reaction forces found from previous Autopipe analysis [8) will be the one used to base the piping load analysis.
In this case, the reaction loads from node 5 are higher than node 140 for the "MAX LVL A" load case [8, pg. 126]. This load case is used because it models the most severe conditions. The forces and moments from node 5 are shown below.
F. = 1341 lbs M,= 241,920 in-lb Fy = 2206 lbs my = 77,820 in-lb F2 = 1786 lbs Mz= 62,592 in-lb The loads are rotated into the local coordinate system shown in Figure 13 based on the coordinate values of nodes 5 and 10 [8]. The converted loads are as follows:
F,' = 2,211 lbs Mx'= 215,233 in-lb Fy' 2206 lbs MY'= 77,820 in-lb Fz'= 315 lbs Mz'= -126,804 in-lb Since the location of the input piping load is on the outside surface of the vessel, it is assumed this location is equivalent to the second cut. Therefore, the L2 is equal to zero and the L1 is with a Revision 0
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negative value for the distance between first cut and second cut (Cut II). The calculations for the safe end and blend radius are shown in Table 4. The first cut location is the same as the Green's Function cross section at the safe end, and the second cut is assumed to be on the vessel ID (i.e.,
Node 5 from the AUTOPIPE model [8]). The maximum stress intensities due to piping loads are 4598.60 psi at the safe end and 343.12 psi at the blend radius, respectively.
Table 4: Piping Load Calculations Safe End External Piping Loads Parameters FX =
2.21 kips Fy =
2.21 kips Fz =
0.31 kips MX =
215.32 in-kips MI =
77.82 in-kips Mz =
-126.80 in-kips OD=
11.00 in ID=
9.375 in RN =
5.09 in L
-18.72 in tN 0.81 in W02 =
256.62 in-kips (My) 2 =
36.43 in-kips Blend Radius External Piping Loads Parameters F= =
2.21 kips Fy =
2.21 kips Fz =
0.31 kips Mx=
215.32 in-kips my =
77.82 in-kips Mz =
-126.80 In-kips OD=
20.00 in ID=
11.140 in RN =
7.79 in L
0.00 in tN =
4.43 in (MA) 2 =
215.32 in-kips (My)2 =
77.82 in-kips 259.19 in-kips 228.95 in-kips FY =
3.12 kips Fxy =
3.12 kips Nz =
3.19 kips/in Nz 1.21 kips/in qN 0.97 kips/in qN=
0.46 kips/in Primary Membrane Stress Intensity Primary Membrane Stress intensity PMz =
3.93 ksi PMz =
0.27 ksi
_ r =
1.20 ksi T =
0.10 ksi SImaX
[
4.60 ksi Simax =
0.34 ksl Simax =
4598.60 psi Simax =
343.12 psi Revision 0
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7.0 PEAK STRESS FACTOR The piping load stress intensity value is also included in Tables 5 and 6. Total stress intensity values for membrane plus bending are obtained by combining the thermal membrane plus bending stress for 4500F, the pressure membrane plus bending stress, and the piping stress intensity. Total stress intensity values for membrane plus bending plus peak are then obtained by combining the total thermal stress for 4500F, the total pressure stress, and the piping stress intensity. These values are also given in Tables 5 and 6.
Maximum (ura,) and steady-state (a,,) values are then determined for the membrane plus bending and total stress cases. Then the maximum possible stress range (2cma,, - Oss) is obtained. The ratio of this range for membrane plus bending over total equals the Peak Stress Factor (PSF), which is calculated for both feedwater locations, as shown in Tables 5 and 6. These values are implemented into FatiguePro. The peak stress factor for the nozzle safe end is 0.677 and the peak stress factor for the blend radius is 0.993. All peak stress calculations are included in the Excel file OCGreenFCN.xls, which is included in the project files.
8.0 CONCLUSION
S The files SE. CLN and BR. CLN contain the stress histories necessary to develop 100% flow Green's Functions. A total stress intensity history Green's Function is produced for each of these files. The Green's Function is calculated by dividing the Total Stress Intensity (sixth column) by the change in temperature. It should be noted that the (Membrane + Bending) column (fourth column) does not always equal the sum of Column 2 (Membrane) and Column 3 (Bending) because the values are stress intensities and therefore vary due to changing magnitudes of stress direction. Tables 5 and 6 and Figures 14 and 15 show the thermal stress histories produced by SE. CLN and BR. CLN.
The project files contain all files associated with this calculation.
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Inputs:
Results:-
Table 5: Safe-End Node 1344 Data AT=
M+B Pressure Stress Intensity, Safe End =
Total Pressure Stress Intensity, Safe End =
Piping Load SImx =
Peak Stress Factor, PSF =
Omax ass u 2
- U'max ' Uss
-450 7,732 7,767 4,599 0.677 57,611 25,261 89960.60 79,616 26,396 132835.60 TIME (sec)
Membran e
(psi)
Bending (psi)
Membrane +
Bending (psi)
Peak (psi)
TOTAL Green's Function (psi)
(psi/F)
MEM+BND Stress Intensity (Thermal+Pressure)
(psi)
TOTAL Stress Intensity (Thermal+Pressure)
(psi) 1.00E-10 0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08 0.09 0.1 20000 35 19 68 117 163 208 252 294 335 375 414 7566 32 267 566 864 1162 1459 1755 2049 2343 2634 2925 9169 64 272 606 937 1266 1594 1919 2243 2564 2882 3199 12930 14 3027 5799 8336 10660 12790 14750 16540 18200 19720 21120 5103 63 3259 6319 9144 11750 14170 16410 18480 20410 22210 23880 14030
-0.14
-7.24222222
-14.0422222
-20.32
-26.1111111
-31.4888889
-36.4666667
-41.0666667
-45.3555556
-49.3555556
-53,0666667
-31.1777778 12,395 12,603 12,937 13,268 13,597 13,925 14,250 14,574 14,895 15,213 15,530 25,261 12,429 15,625 18,685 21,510 24,116 26,536 28,776 30,846 32,776 34,576 36,246 26,396 Note: The actual EXCEL spreadsheet (OCGreenFCN.xls) contains more time points than are shown here.
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Inputs:
Table 6: Blend Radius Node 584 Data aT=
M+B Pressure Stress Intensity, Blend Radius=
Total Pressure Stress Intensity, Blend Radius=
Piping Load SImAx =
Peak Stress Factor, PSF =
Omax =
2 as =
2 (max " oass=
-450 53,150 56,070 343 0.993 85,033 85,033 85033.12 Results:
85,673 85,673 85673.12 BnngMembrane +
TIME Membrane Bending enn Bending (sec)
(psi)
(psi)
(psi)...
TOTAL MEM+BND TOTAL Green's Stress Intensity Stress Intensity Function (Thermal+ Pressure) (Thermal+Pressure)
(psi)
(psi)
(psi/F)
(psi)
(psi) 1.OOE-10 0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08 0.09 0.1 20000 3160 3162 3161 3160 3161 3158 3162 3156 3162 3154 3163 3151 3163 3149 3164 3147 3164 3145 3165 3143 3165 3141 13630 18030 6274 6273 6272 6271 6270 6269 6268 6267 6267 6266 6265 31540 1196 5886
-13.08 1196 5896
-13.1022 1196 5907
-13.1267 1197 5917
-13.1489 1197 5927
-13.1711 1199 5937
-13.1933 1200 5948
-13.2178 1202 5958
-13.24 1204 5968
-13.2622 1206 5978
-13.2844 1209 5988
-13.3067 9486 29260
-85.0222 59,767 59,766 59,765 59,764 59,763 59,762 59,761 59,760 59,760 59,759 59,758 85,033 62,299 62,309 62,320 62,330 62,340 62,350 62,361 62,371 62,381 62,391 62,401 85,673 Note: The actual EXCEL spreadsheet (OC GreenFCN.xls) contains more time points than are shown here.
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Green's Function - Safe End Location 0*
0
-20
-40
-60
-80
-100
-120
-140
-180 0
20 40 60 80 100 0i"e (soe) 120 140 160 180 200 Figure 14: Safe-End Node 1344 Green's Function
Green's Function - Blend Radius Location
-10
-20 -40..
-50
-600
-70 0
20 40 50 80 100 120 140 10 150 200 time (sC)
Figure 15: Blend Radius Node 584 Green's Function
9.0 REFERENCES
- 1. MPR Report No. MPR-783, "Oyster Creek Nuclear Generating Station Evaluation of Low Flow Feedwater Control System," August 1983, SI File No. OC-05Q-205.
- 2. ANSYS Release 8.1 (with Service Pack 1), ANSYS, Inc, April 2004.
- 3. Structural Integrity Report Number SIR-88-028, Revision 0, "Operating Instructions Feedwater and CRD Return Nozzle Thermal Transient Monitoring System Oyster Creek Nuclear Generating Station," September 16, 1988, SI File No. GPUN-13-101.
- 4. General Electric, Co. Drawing No. 232-566, "Nozzle Details - Vessel," Revision 6, 9-3-64, SI File No. OC-05Q-232.
- 5. ASME Boiler and Pressure Vessel Code,Section II, Part D - Properties, 1995 Edition (with 1996 Addenda).
- 6. E-mail from Michael J. May (OC) to Gary Stevens (SI) dated September 24, 2004,
Subject:
"Heat Balance," Attached "Heat Balance OC.pdf," SI File No. OC-05Q-228.
- 7. EPRI Report No. TR-107448, "FatiguePro, Version 2: Fatigue Monitoring Software," December 1997.
- 8. GPU Nuclear Report No. C-1302-422-E540-046, "Oyster Creek NSR Pipe Analysis, Feedwater System Reactor Nozzles N-4A & N-4B thru penetration X-4A to Anchor 422-14," Revision 2, January 2001, S1 File No. OC-05Q-217.
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APPENDIX A: COMPUTER INPUT AND OUTPUT FILES Revision 0
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The following list of electronic files is included in the project files:
FILENAME DESCRIPTION BR FLW.OUT Blend Radius Stress Intensity output file from extraction of Thermal Load application BR PRES FLW.OUT Blend Radius Stress Intensity output file from extraction of Pressure Load application OC_FWNGEOM.INP Ansys input file for creation of Nozzle Geometry OC FWNPRES.INP Ansys input file for application of pressure loads OCFWN THM. INP Ansys input file for application of thermal transients OC FWN THSTR.INP Ansys input file for application of thermal shock OC GreenFCN.XLS Excel file containing Safe End and Blend Radius Green's Functions SE FLW.OUT Safe End Stress Intensity output file from extraction of thermal shock application SE PRES FLWOUT Safe End Stress Intensity output file from extraction of pressure load application FWN HT COEFF.XLS Spreadsheet that generates Heat Transfer Coefficients BR.CLN Output file containing raw information for Blend Radius location Green's Function SE.CLN Output file containing raw information for Safe End location Green's Function XTR BR-POS Stress Intensity extraction file for Blend Radius location from Thermal Load application XTR BR PRES.POS Stress Intensity extraction file for Blend Radius location from Pressure Load application XTR SE.POS Stress Intensity extraction file for Safe End location from Thermal Load application XTR SE PRES.POS Stress Intensity extraction file for Safe End location from Pressure Load application Listed Files in Appendix A:
OCFWNGEOM.INP A3-A7 OCFWNPRES.INP A8-A9 OCFWNTHM.INP A10-A14 OCFWNTHSTR.1NP A15-A16 XTRBR.POS A17 Revision 0
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OCFWNGEOM.INP Ifinish I/clear,start
!/config,'nes, 100000 1/fdn,OCFWN_GOM l/prcp7 let,l,planc42.,,1 1! Geometry fbr Oyster Creek Feedwater Nozzle I!
1 Material I (Reactor Vessel Plate SA 302 Grade B) mp,ex,1,2.79E+07 mp,alpx,l,7.81E-06 mp,kxx, 1,24.7/3600112 mp,c,l,0.1215 mp,nuxy,1,0.3 mp,dens,1,0.283 1 Material 2 (Nozzle Forging SA 336) mp.ex,2,2.84E+07 mp, apx,2,7.395E-06 mp,kxx,2,23.8V3600/l2 mp~c,2,0.121 mp,nuxy,2,0.3 mp,dens,2,0.283 1 Mateial 3 (Safe End SA-105 Gr.il) mp,ex,3,2.80E+07 mp,alpx,3,7.325E-06 mp,kxx,3,28.2/3600/12 mp,c,3,0.122 1 mp,nuxy,3,0.3 mp,dens,3,0.283 I Geometry
- AFUN,deg local, 13,1,,,,,-90, csys,13 1 0,0 is at the end of dhe Safe End, center line
! inner radius geometry - keypoints k, 1,4.6875%0 k, 2,4.6875,,3,844 k, 3,4.914.,4.75 k, 4,4.914,,5.75 k, 5,5.1015,,6.5 k, 6,5. 1015,,20.003 k, 7,5.57 _21.875 1 outer radius geometry - keypoints k, 8,5.5,,0 k, 9,5.5
,0.75 Revision 0
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1,10,5.5
,,0.93957 k,11,5.5
,,3.625 k,13,5.9375,5.75 k,14,5.9375 J1.0625 k,15,9.625,,14.75 k,16,9.625 _25 k,19,5.57,,40 1,7,19 k,50,5.5
,-6 k,51,4.6875,,-6 I lines connecting inner/outer radius keypoints 1,1,2 1,2,3 1,3,4 1,4,5 1,5,6 1,6,7 1,50,51 1,8,9 1,9,10 1,10,11 1,11,13 1,13,14 1,14,15 1,15,16 Creating vessel wall local, 14,1,,371.12,,.
k,21,.,0,0 k,17,341.501,270,0 k,18,341.501,299,0 k,20,348.626,299,0 k,21,348.626,270,0 1,17,18 1.20,21 1,18,20 lintcr,15,17 Idele,20 lintcr, 16,1 Idele,17 Idele,23 Idele,22 k,24,341.501,271.492674 k,25,343.7096,270 1,24,25 lintcr,l,15 Iinter,22,20 Idelc,15 Idele,17 Idclc,23 I Creating Fillets Ifillt,19,21,2375
Ifillt,13,14,1 Ifillt,14,19.1 Ifillt,3,4,0.125 Ifillt,4,5,0.125 filit,5,6,0. 125 IfilLt,1622,2.125 Jfillt,2,3,0.125 1dclc,9,11,1 ldele,2 1,2,51 1,11,50 I Mapping Vessel Wall MSHKEYI Mapped Meshing - user defined MAT,l csys,13 k,53,10.625,,15 t Additional geometry k,54,10.625,,35 1,53,54 linter,10,15 linter,1,30 Idele,32 Idele,29 1,26,39 k,55,17.5,,15 k,56,17.5,,35 1,55,56 linter,10,29 linter,21,33 ldele,34,36,2 lesize,8,,, 10 lesize,35,_,l0 lesize,30,,,40 lesize,10,,,40 al,35,30,18,10 I AREA I ldelej lesize,31,,, 10 lesize,32,,, 10 lesize,29,,,8 lesize,28,.2 al,31,32,35,29,28 1 AREA 2 Comer - Nozzle Forging I Creating 2 pie shaped pieces - this is the first Mat,2 kl,11,0.5,60 1,60,38 linter, 1,26 linter, 1, 11 lesizl.,10 lesizn,26.,5 lesize,22...3 Icsizc,15.,2 lesize,33.,I 0 al,33,1,26,22,15,31 ! AREA 3 I Creating second pie shape Revision 0
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1,6,26 lesizc,1,,,10 lesize,21,,. 12 Iesize, 1 6,9 lesize,7,,,3 a&,21,11,7,16,1 1 AREA 4
! Meshing the final portion of the Nozzle End forging csys, 13 k,70, 5,,7.8125 I Additional Geometry k,71,6,,7.8125 1,70,71 linter,6,34 Idele,38 linter,13,39 Idele,40 kl,36,0.4,73 kl,36,0,765,74 1,31,73 1,28,74
! First section (3) of the final portion of nozzle end forging linter,13,36 linter,39,41 lesize,13.,10 lesize,19,,10 lesize,40,,, 10 al, 11,19,13,40 1 AREA 5
! Second section (3) of the final portion of nozzle end forging lesizc,39,.10 lesize, 17,,,2 lesizc,14.,,8 lesize,20,,,2 lesize,42,,, 12 ai,39,17,14,20,42,13
! AREA 6 Third section (3) of the final portion of nozzle end forging Iesize,38,,, 10 lesize,36.,5 lesize,34,,.5 al,34,39,36,38 I AREA 7 I Creating the first mesh (3) of Safe End Mat,3 1,34,13 1,40,11 lesize,37,,,6 lesize,25., 1 lesize,5,,,4 lesize,24.,.l lesizc,4 ],,,I0 lesize,6,,,12 al,37,25,5,24,41,6,38 I AREA 8 Revision 0
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1 Creating the second mesh (3) of Safe End lesizc,4.,4 lesize,23.. I lesize,3,.4 lesize,27,. )
lesize,43.,IO lesize,12.,,0 al,41,12,43,27,3,23, 4 1 AREA 9
! Complete the finrl section--something wrong with Geonetry...
ldele,2 1,40,51 lesize,g,.10 lesize,2...15 lesizc,9,... 5 al,2,8,9,43 I AREA 10 I Concatenating lines for Meshing Iccat,28.29 I For Area 2 flst,2,3,4,orde,3 I For Area 3 fitem,2.15 fitem,2,22 fitem,2,26 lccat,p5lx lccat,7,16 1 For Area 4 FLST,2,3,4,ORDE,3 I For Area 6 FITEM,2,14 FITEM,2,17 FITEM.2,20 LCCAT,P5 IX FLST,2,4,4,ORDE,4 I For Area 8 FITEM,2,5 FITEM,2,24 FITEM,2,-25 FITEM,2.37 LCCAT,P5IX FLST,2,4,4,ORDE,4 I For Area 9 FITEM,2,3 FITEM,2,-4 FITEM,2,23 FITEM,2,27 LCCAT,P51X
! Creating Meshes from areas Mat, t I Meshing for Material I Areas amesh,1,2,1 mat,2
! Meshing for Material 2 Areas amesh,3,7,1 mat,3 I Meshing for Material 3 Areas amesh,8,lO, !
IPNUM,LINE, 1
/PNUM,KP,I Iplot Revision 0
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OCFWNPRES.INP finish
/clear,stet
/config,nres,100000
/filnOC_FWNSTR
/prep7 I Oyster Creek
/tide, Feedwater Nozzle Finite Element Model 2D model for generating Grwne's Functions et I,plane42,,, I axisymmetric
/input,OCFWN GEOM,inp 11 Boundary Conditions I!
I Coupled Nodes on the Nozzle Safe End FLST,5,I i,I,ORDE,3 FITEM,5,1343 FITEM,5,1358 FITEM,5,-1367 NSEL,S,,,P51X cp,l,uy,aIl I Symmetry Conditions nsel,all DL, I 8,,SYMM,,
/solu
! Define Pressure Value and Cap Load
- set,Pressure,l000 I Pressure (psi), internal pressure applied
- set, PCAP, Pressure*((24.6875)**2)/((2*5.5)**2-(2*4.6875)**2) 1 *4 Apply Cap Load*"
SFL,8,PRES,-PCAP
- Apply Pressure Load
- SFL, 2,PRES,Pressure ! ID of Safe End SFL,27,PRES,Pressure I ID of Safe End SFL, 3,PRES,Pressure I ID of Safe End SFL,23,PRES,Pressure I ID of Safe End SFL, 4,PRES,Pressure I ID of Safe End SFL,24,PRES,Pressure I ID of Safe End SFL, 5,PRES,Pressure I ID of Safe End SFL,25,PRESPressure I ID of Safe End SFL,37,PRES,Pressure I ID of Safe End SFL,36,PRES,Prcssure I ID of Nozzle Forging SFL,42,PRES,Pressure I ID of Nozzle Forging SFL,40,PRES,Pressure I ID of Nozzle Forging SFL, 7,PRES,Pressure I ID of Nozzle Forging SFL,16,PRES,Pressure ID of Nozzle Forging SFL,26,PRES,Pressure ID of Nozzle Forging SFL,22,PRES,Pressure I ID of Nozzle Forging SFL,15,PRESPressure I ID of Nozzle Forging SFL,32,PRES,Pressure I ID of Vessel Wall Revision 0
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SFL,30,PRES,Pressure ! ID of Vessel Wall SOLVE SAVE FINISH
/ANG, 1,30,ZS, I
/REPFAST
/ANG,I,30,ZS,l
/REP,FAST
/ANG,i,30,ZS,1
/REP,FAST 0
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OCFWNTHM.INP finish
/clear,start
/config~nres, 100000
/filn,OCFWNTHM
/prep7 I Oyster Creek Feedwater Nozzle
/title, 2-D Axisymmetric OC Feedwater Nozzle FEM for Green's Functions et, l,plane55,.1
!Axisymmetric
/input,OCFWN-GEOM,inp MI IM!! ! !I! !M!!!! I IIM
!! Boundary Conditions
!MII MIl I I! I!!!!!!! M!M I Coupled Nodes on the Nozzle Safe End FLST,5, 11,1,ORDE,3 FITEM,5,1343 FITEM,5,1358 FITEM,5,-1367 NSEL,S,,,P5IX cp,l,uy.all 1 Symmetry Conditions DL, I 8,,symm
/solu I !!! I t
M!!!l! ! !!!!
W I!
l !!!
I Thermal Boundary Conditions I I !!1!11!I!!
!!!!! I !! !!! !!!!!!!I I!!
I Heat Transfer Coefficients - Steady State Tamb=70 I Ambient Temperature hl=205.1/(3600*144)
I Safe End h2-205.1/(3600- 144)
I Nozzle Forging step I h3=205.1/(3600* 144) 1 Nozzle Forging step 2 h4=205.1/(3600" 144)
! Vessel Wall h5=(h I+h2)/2 I Thermal sleeve rest ho00.2/(3600* 144)
I Outside Heat Temperature Coefficient T1=550 T2-550 T3=550 T4=550 TS=550
/solu
!I Load Step I - Steady-State, No Flow II MI!
AplyH!!!IIs!!f IIIII I!MMM I Apply HTC'$
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! Region I SFL, 2,CONV,hJ,,T I SFL,27,CONV,hl,,TI SFL, 3,CONVhl,h5,TI,T5 1 Region 5 SFL,23,CONV,h5.T5 SFL, 4,CONVhS,,T5 SFL,24,CONV,h5,,T5 SFL, 5,CONV,h5,h2,TS,T2 I Region 2 SFL,25,convh2LT2 SFL,37,conv)h2.T2 SFL,36,conv,h2.,T2 SFL,42,conv,h2,T2 SFL,40,conv,h2.T2 SFL, 7,conv,h2,h3,T2,T3 I Region 3 SFL,I6,conv,h3.T3 SFL,26,conv,h3,h4,T3,T4 1 Blend Radius 1 Region 4 SFL,22,conv,h4,,T4 SFL, I 5,convh4.T4 SFL,32,conv,h4,T4 SFL,30,conv,h4,,T4 SFL,1 8,onv,ho.Tamb SFL, I0,convho,,Tamb SFL,29,conv,ho.Tamb SFL,28,conv,ho.Tamb SFL,33,convho.,Tainb SFL,21,conv,ho.Tamb SFL.19,conv,ho,,Tarnb SFL,20,conv,ho.Tamb SFL,14,conv,hoTamb SFL,1 7,conv,ho.Tamb SFL,34,conv,ho,,Tamb SFL, 6,onv~ho,,Tamb SFL,12,conv,ho,,Tamb SFL, 9,conv,ho,,Tanb SFL, 8,convho,,Tanib 11Perform Steady State Run mImm!!
fiif! Fr rriimi ANTYPE,TRANS allselall outresaIl,all TIMINT,off TIME, Ic-10 SOLVE SAVE H !! I!!!! !
1! Load Step 2 1 Revision 0
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I Heat Transfer Coefficients - Shock hl-2108.8/(3600"144) b2-673.9/(3600* 144) h3=191.8/(3600#144) h4=1000/(3600* 144) h5=(hl+h2)/2 ho--0.2/(3600 144)
I Safe End I Nozzle Forging step I 1 Nozzle Forging step 2 I Vessel Wall I Thermal sleeve rest 1 Outside Heat Temperature Coefficient TI=100 T2=325 T3=325 T4=550 T5=325
/solu II Load Step 2 - Thermal Shock - Max Flow I!
I!IIIII!
IIIIIIII !!I!!I!! III!!! !!! I!!II!
1 Region I SFL, 2,CONV,hI,,T SFL,27,CONV,hl,,TI SFL, 3,CONV,h I ",T1,T5 1 Step Region SFL,23,CONV,hS,,T5 SFL, 4,CONV,hS.,TS SFI,27,CONV,h5,,T5 SFL, 5,CONV,hS5h2T5,T2 I Region 2 SFL,25,convX,h,T2 SFL,37,conv,h2,,T2 SFL,36,conv,h2,,T2 SFL,42,conv,h2,,T2 SFI,40,oonv,h2,,T2 SFL, 7,conw,h2,h3,T2,T3 I Region 3 SFL,16,cDnv,li3,,T3 SFL,26,convji3,h4,T3,T4 I Region 4 SFL,22,conv,h4,,T4 SFL, I 5convjs4,,T4 SFL,32,c~onv,h4,,T4 SFL,30,conv,h4,.T4 SFL,18,c~onv,ho,,Tsnib SFL,I 0,conv,ho,,Twnb SFL,29,conv,ho,,Taumb SFL,28,conv~bo,,Tamb SFL,33,eonv,ho.,Tamb SFL.21,cnv,ho,,Taemb SFL,19,conv,ho,,Tarnb SFL,20,oonvjho,.Tamb SFL,14,rconvjio.,Tamb SFL, 17,conv~ho,,Taznb SFL,34,conv,ho,.Tamb I Blend Radius Revision 0
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SPL, 6.conv,ho,,Tanib SFL,12,conv,ho,,Tamb SFL. 9.conv, ho, Tamb SFL, 8,conv,hoTamb I Load Step 2 - Thermal Shodc nsel,all csl,adl outres, alall KBCI TnIINT,ON AUTOTS,OFF NSUBST,300, TIME,3 SOLVE SAVE i Load Step3 nselal esel,all outres,all,all KBCl TIMINT,ON AUTOTS,OFF NSUBST,70, TIME, 10 SOLVE SAVE I Load Step 4 nselall esel.all outresall,all KBC,l TIMINT,ON AUTOTS,OFF NSUBST,900, TIME,100 SOLVE SAVE I Load Step 5 nselall esel, al outres'allall KBC,l TIMINT,ON AUTOTSOFF NSUBST,900, TIME,!000 SOLVE SAVE
.1 Load Step 6 nsel,all eselall outres,all,all Revision 0
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KBC,I TIMINT,ON AUTOTS,ON NSUBST, 100,200, 10 NROPT,AUTO,,ON TIME,20000 SOLVE SAVE FINISH Revision 0
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OCFWNTHSTR.JNP finish
/clear,start
/CONFIGNRES,IOOO00
/FILNOC FWNTS
/prep7 1, Oyster Creek Nuclear Power Plant
/titde, Feedwater Nozzle Finite Element Model
/com, title, 2D Model for generating Greene's functions ct,l,plane42_,1
! axisymmetric
/input,OCFWNGEOM,inp i1 Boundary Conditions t I Coupled Nodes onthe Nozzle Safe End FLST,5,1 I,lORDE,3 FITEM,5.1343 FITEM,5,1358 FITEM,5,-1367 NSEL.S,,,P5IX cp,l,uy,all
! Symmetry Condilions nsel,all DL,I8,,SYMM,,
/solu
- ,********0************
/COM, Read Thermal Stress Tref,70
/COM, LOAD STEP 1, STEADY STATE Idrcad,temp,,,I1-10,,OCQFWN_THM,rth timele-10 solve
/COM, LOAD STEP 2, FIRST THREE SECONDS
- doi.0.01,3,0.01 ldread,tcmp,,,i,,OCFWNTHM,rth time,i solve
- enddo
/COM, LOAD STEP 3
- do,i,3.I,10,0.1 ldread,temp.,i,,OCFWNTHM,rth time,i solve
- enddo
/COM, LOAD STEP 4
- do,i,10.2,100,0.1 ldread,temp,,,i,,OCFWN_THM,rth timeji solve Revision 0
Preparer/Date EEJ 07/20/2005 Checker/Date MQ 07/20/2005 File No.
OC-05Q-307 Page A15 of A17
- enddo
/COM, LOAD STEP 5
- do,i,101,1000,1 Idread,tem,,,i,,OCFWNTHM,rth time,i solve
- enddo ICOM, LOAD STEP 6
- do,i,1200,20000,200 ldread,tcmp,,i,,OCFWN_THM,rth time,i solve Oenddo SAVE FINI
!/INP, XTRFLWPOS Revision 0
V Preparer/Date EEJ 07/20/2005 Checker/Date MQ 07/20/2005 File No.
OC-05Q-307 Page A16 of A17
XTRBR.POS csYs,O
/postl
/outBR-FLW,out r= 6.2964 avprin,0,0, csys,0 fist,2,2,1 fitem,2,584 fitem,2,570 path,br,2,30,20 ppath,p51x,l set,,,l,,l-10 pmapACCURATE,'
prsect,r,0
- doi,0.0,3,0.01 set...
I,,i pmap,ACCURATE,'
prsectr,0
- enddo
- do,i,3.1,10.0.1 set,,,,,i pmapACCURATE,'
prsect,r,O
- enddo
- do,i,10.2,100,0. I set,,,I,i pmapACCURATE,'
prsect'r,0
- enddo
- do,i,101,1000,1 set,,,I,i pmap,ACCURATE,'
prsect,r,0
- enddo I output safe end linearized stress to file I
I
- do,i,1200,20000,200 setm..1,i pmap,ACCURATE,'
prsect,r,0
- enddo
/out Revision 0
V Preparer/Date EEJ 07/20/2005 Checker/Date MQ 07/20/2005 File No.
OC-05Q-307 Page AI7 of A17