ML20095L105
| ML20095L105 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1991 |
| From: | Hughes E EG&G IDAHO, INC. |
| To: | NRC |
| Shared Package | |
| ML20095L113 | List: |
| References | |
| CON-FIN-L-1696 EGG-NE-10184, NUDOCS 9205060221 | |
| Download: ML20095L105 (15) | |
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TECHNICAL EVALUATION REPORT TUE-1 DEPARTURE FROM NUCLEATE BOILING CORRELATION E.D. Hughes W.C. Arcieri December, 1991 b EG&G Idaho -Inc.
Idaho Falls, Idaho 83415 Prepared for the U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-761001570 FIN. No. L1696 Task Order No. 4
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ABSTRACT j An evaluation of the departure from nucieete boiling correlation developed by l
- Texas Utilities Electric Company was performed. The correlation is an i empirically derived function ol the local coolant thermodynamic state and mass flux at which departure from nucleate boiling (DNB) is observed to occur. The ;
correlation is designated as TUE 1 and will be used by TV Electric to support
'b t operational transient analysis for licensing and safety calculations for ;
the Comanche Peak-Steam Electric Station (CPSES).
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SUMMARY
This report documents the review and evaluation of the TUE 1 departure from nucleate boiling correlation developed by Texas Utility Electric Company.
This correlation is developed to evaluate the DNB heat flux for Westinghouse 17x17 fuel assemblies with R type mixing vane grids and Advanced Nuclear Fuel (ANF) 17x17 fuel assemblies. TV Electric reports RXE-88-102 P and RXE 102 P, Supplement in.2) documenting the development of the TUE-1 DNB correlation for _these fuel designs were schnitted to the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission (NRR/NRC) for epp.roval in performing operational transient analysis fer licensing and safety analysis at Comanche Peak. The NRR/NRC staff recuested assistance from the Idaho National Engineering Laboratory (INEL) in reviewing the TUE-1 correlation.
The review consisted of evaluating the TUE-1 correlation, the data base supporting development of correlation, and the statistical characterization of the correlation. The review was performed using the information provided by TV Electric as documented in RXE-88-102-P and RXE-88-102-P, Supplement I and the responses to the requests for additional information submitted by the NRR/NRC to TV Electric regarding the development and use of the correlation.
Based on_this review, it is recommended that the TUE-1 correlation be accepted fer assessments :( departure from nucleate boiling during operational transients at Comanche Peak for the Westinghouse 17x17 fuel assemblies with R type mixing vane gr 6:. Arre the ANF 17x17 fuel assemblies subject to the restrictions presentec , Section 3 of this report.
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t TABLE OF CONTENTS CONTENTS Pace No ABSTRACT' ..................................................... i
SUMMARY
...................................................... 11 TABLE OF CONTENTS ............................................ iii
- 1. INTRODUCTION ........................................... 1
- 2. TUE-1 CORRELATION ...................................... 3 2.1 Description of the TUE-1 Correlation .............. 3 2.2 Data Base, Prodictive Capability and Statistical Capability ....................................... 4
- 3. RESTRICTIONS ........................................... 7
- 4. CONCLUSIONS ............................................ 9
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REFERENCES ............................................. 10 TABLES
- Range of Application for the TUE-1 Correlation .......... 8 APPENDICES APPENDIX A - Request for Additional Information for the TUE-1 Correlatica Review iii
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1.0 INTRODUCTION
The TUE 1 correlation was developed by Texas Utilities Electric Company for assessing the departure from nucleate boiling (DNB) for Westinghouse 17x17 fuel with R-type mixing vane grids and Advanced Nuclear Fuel (ANF) 17x17 fuel assemblies at typical reactor operating conditions at the Comanche Peak Steam Electric Station. Comanche Peak is a two unit Westinghouse 4-loop pressurized water reactor (PWR) utilizing Westinghouse 17x17 fuel with R-type mixing vane 0
grids. TU Electric reports RXE-88-102 P and RXE-88-102-P, Supplement 1 '22 documenting the TUE-1 correlation were submitted to the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission (NRR/NRC) by TV Electric for review and acceptance for licensing applications as a method to assess the DNB safety limit for operational transient analysis in support of fuel reload at Comanche Peak in a manner that conforms to NRC requirements.
The NRR/NRC is responsible for the evaluation and review of computer codes, analysis methods, and their proposed application. The NRR/NRC requested assistance from the Idaho National Engineering Laboratory (INEL) in reviewing
- the TUE-1-correlation for predicting DNB. Specifically, the request for assistance included:
- 1. Evaluation of the correlation.
- 2. Evaluation of the correlation data base and experimental measurements used to develop _the correlation.
'3. Evaluation of the statistical characterization of the TUE-1 correlation and uncertainty treatment.
Following the above review, NRR/NRC requetted additional information from TV Electric. The INEL reviewed and evaluated the TV Electric responses to NRR/NRC questions regarding the development and use of the correlation. The responses to the requests for additional information are contained in Appendix A to this report.
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This technical evaluation repott contains the results of the review of the TUE-1 correlation for application to operational transient analysis for fuel reload at Comanche Peak. Section 2 provides a discussion of the correlation, the experimental basis, and statistical development. Section 3 identifies the restrictions to be imposed on the application of the correlation for licensing purposes, while Section 4 summarizes the conclusions from the TUE-1 correlation review.
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4 2.0 TUE-1 CORRELATION This section presents a brief description of the TUE-1 departure from nucleate boiling correlation discussing the correlation, the experimental basis upon which it was ~ developed, the statistical characterization of the correlation and its intended applications.
2.1 Description of the TUE-1 Correlation The TVE-1 correlation was developed by TV Electric for application to licensing and safety calculations regarding the assessment of operational transients for Comanche Peak. The TVE-1 correlation was developed specifically for evaluation of Westinghouse 17x17 fuel with R-type mixing varie grids and Advanced Nuclesr Fuel (ANF) 17x17 fuel assemblies for typical reactor operating conditions at Comanche Peak.
The TVE-1 correlation is _ an empirically derived correlation which has the following form:
QDNB = E - F
- X Where:
QDNB is the predicted DNB heat flux, X is the local equilibrium quality, E and F are functions of parameters such as grid spacing, mass flux, system pressure, etc.
The correlation is based on data derived from experiments on test assemblies to determine the measured heat flux at DNB as a function of fuel geometry and thermal hydraulic conditions. Experimental data based on uniform and non-uniform power distributions were also obtained and the correlation includes factors for both geometry and non-uniform axial power distributions. The VIPRE-01 computer program was used to perform the subchannel analysis"' to determine the predicted heat flux. Provisions are also included in the VIPRE-01 simulation of the fuel assembly to accommodate turbulent mixing which affects the enthalpy transport between subchannels due to turbulent exchange 3
and diversion crossflow. Statistical analysis was also performed on the ratio of minimum predicted DNB heat flux to measured DNB heat flux (MDNBR) to check for bias, statistical combinability and to determine the DNBR limit at a 95 percent probability at a 95 percent confidence level.
2.2 Data Base, Predictive Capability and Statistical Capability The data base used to develop the TUE-1 correlation for Westinghouse 17x17 fuel consists of 934 data points taken from the Columbia Univc.sity DNB experimental data bank. This data bank includes over 11,000 points from a total of 235 test sections compiled over a 20 year period at the Columbia University Heat Transfer Research Facility and was published in 1982. This data was selected for the TUE-1 data base since it is considered to be representative of Westinghouse fuel with R type mixing vane grid design. The TUE-1 correlation was also evaluated for appl:ication to analysis of the ANF 17x17 fuel based on data developed specifically for the fuel design.
Data for Westinghouse fuel is based on test sections with a R type mixing vane grid design and a grid spacing from 20 to 32 inches. These test sections consisted of 4x4 and 5x5 rectangular arrays of rods with heated lengths of 8 and 14 feet. _The 4x4 array has a rod outer diameter of 0.422 inch, which is representative of Westinghouse 15x15 fuel. The 5x5 array has a rod outer diameter of 0.374 inch, which is representative of Westinghouse 17x17 fuel.
The data base includes both uniform and non-uniform axial heat flux profiles.
The non-uniform profiles include cosine or usine(u) top peaked shapes. RXE-88-102-P notes that several test sections contained unheated rods to simulate control rod guide thimble tubes for analysis of the " cold wall" effect.
The 934 data points compiled for development of the TUE-1 correlation for Westinghouse 17x17 fuel excludes 34 points in the original Columbia DNB data.
The reasons for excluding these-points cited in RXE-88-102-P are: 1) 25 points were based on thermal hydraulic conditions outside the range of application for TUE-1, and 2) nine points were found to be statistical outliers based on an evaluation using Chauvenet's criterion.
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The TUE-1 correlation was incorporated into the VIPRE-01 computer program and analyses performed to determine the predicted DNB heat flux for each test point in the data base. The ratios of the predicted DNB heat flux to the measured heat flux or MDNBR was used in a statistical analysis to measure the ability of the'TUE-1 correlation, as incorporated into VIPRE-01, to predict the DNB heat flux. The VIPRE-01 analyses utilized the EPRI void model and the Columbia /EPRI two phase multiplier for this analysis.
The overall mean of the distribution from the VIPRE analysis was determined to be 1.0018 with a standard deviation of 0.0884 as presented in RXE-88-102-P.
Statistical tests to check that the data is normally distributed and to check statistical combinability were performed. The data were found to be normally distributed based on application of the D' test. Statistical combinability to determine whether the correlation is biased to any particular group of experimental data was tested using Bartlett's test and the general F test in RXE-88-102 P. The data were found to be statistically combinable with the exception of the axial heat flux profile group. RXE-88-102-P states that the correlation prediction is not biased to any particular subgroup of data since the mean of each subgroup is within one percent of the mean of the entire data set. The standard deviation of all of the subgroups of data are within one percent of the 8.84 percent standard deviation of the entire data set.
The 95/95 DNBR limit was determined using Owen's one-sided tolerance limit factor. Based on this calculation, the 95/95 DNBR limit was calculated to be 1.1547 which is rounded to 1.16.
The TUE-1 correlation was evaluated for application to analyses involving ANF 17x17 fuel as described in RXE-88-102-P, Supplement I using DNB data developed for ANF fuel. The procedure used is the same as that described above for Westinghouse fuel. The TUE-1 MDNBR limit of 1.16 was determined to also be applicable to ANF fuel. The effect of a mixed core on DNB was not discussed
'in RXE-88-102-P, Supplement 1. In this case, a mixed core refers to loading both Westinghouse and ANF fuel in the same core. These fuel types could be geometrically different which could affect the DNB predictions. No l adjustment for a mixed core is included in the TUE-1 DNBR limit of 1.16.
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In the INEL evaluation of the TVE-1 correlation, a random numerical check was performed to confirm t...t the conditions presented in Appendix A of RXE 102 P satisfy the TUE-1 correlation for uniform axial heat flux.
The INEL evaluation confirmed the TV Electric analysis. In addition, a parametric anal'y sis of the TUE-1 correlation was performed to determine how well the correlation extrapolates outside of its intended data range. It was found that significant errors can result if the TVE-1 correlation is applied outside_of its data range.
The response to the request for additional information regarding the statistical basis of the correlation, the use of the term boiling length, and -
extrapolation of the TVE-1 correlation outside of its data range was provided by TV Electric and is presented in Appendix A. The responses were found to be acceptable, although it is required that checks be included in the VIPRE code to print a warning message in the code output if the correlation is inadvertently used outside its range of validity. TV Electric notes that DNB will be assumed to occur if any of the calculated conditions are outside the range of the TVE-1 correlation.
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3.0 RESTRICTIONS Based on results of the review of the TV Electric TUE-1 DNB correlation, the following restrictions are identified:
3.1 The TUE 1 DNB correlation shall be restricted to evaluations of the Westinghouse 17x17 fuel with R-grid mixing vane fuel or ANF 17x17 fuel for the range of fuel design parameters given in Table 1.
3.2 Should any of the conditions fall outside the ranges identified in restriction 3.1 above, then DNB shall be assumed to occur.
3.3 The use of the TUE-1 DNB correlation shall be limited to assessments with the VIPRE-01 computer code as described in RXE-88-102-P. Application is restricted to VIPRE-01 since other codes may not predict the same local hydraulic conditions as that calculated by VIPRE-01, which was used to develop the correlation and predict the test data.
3.4 The VIPRE-01 computer program shall be modified to clearly identify in the output from the code that the geometric or thermal hydraulic conditions have fallen outside of the range of application for the TUE-1 correlation.
3.5 The TUE-1 DNB correlation is to be used only for evaluation of steady state overpower and Chapter 15 transients, excluding LOCA, at the Comanche Peak Steam Electric Plant.
The review contained herein pertains only to an assessment of the development of the TUE-1 DNB correlation only. While the VIPRE-01 subchannel code was used to perform analyses of the test data and is documented in TV Electric report RXE-89-002, this review does not represent the technical review necessary to determine the' acceptability of the_ use of the VIPRE-01 code for specific reload licensing applications. As such, the technical review contained herein pertains only to the TUE-1 correlation itself. The use of the VIPRE-01 code with modifications to address the prediction of the Columbia University test data was found to be acceptable only for its use in developing the TUE-1 correlation.
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e Table 1 Range of Application for the TUE-1 Correlation Pressure: 14B5 to 2435 psia 2
local Mass Flux: 0.93 to 3.53 M1bm/hr-ft Lacal Quality: -0.15 to 0.30 a
Local Heat Flux: 0.14 to 1.15 MBTU/hr-ft inlet Subcooling: 30 to 350 BTU /lbm
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Mixing Vane Grid Spacing: 20 to 32 inches Heated Length: 96 to 168 inches Wetted Hydraulic Diameter: 0.37 to 0.51 inches Heated Hydraulic Diameter: 0.46 to 0.58 inches Note:
Range of application data taken from page 2-5 of RXE-88-102-P.
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4.0 CONCLUSION
S The TUE-1 correlation was submitted for approval for use by TU Electric i..
evaluating DNB for Westinghouse 17x17 fuel with R grid mixing vane fuel and ANF 17x17 fuel'for the Comanche Peak Steam Electric Station. The review and evaluation of the data base, development of the TUE-1 DNB correlation, and statistical characterization has demonstrated that the correlation is acceptable for steady state overpower conditions and reload applications to Chapter 15 transient analyses, excluding LOCA. It is noted that the DNBR limit of 1.16 does not include any adjustment for when a mixed core is analyzed. It is therefore recommended that the TUE-1 correlation be accepted for use by TV Electric for operational transient assessment at the Comanche Peak Steam Electric Plant, subject to the restrictions identified in this Technical Evaluation Report.
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5.0 REFERENCES
- 1. Huan B. Giap-and Yi-Xing Sung, TUE-1 Departure From Nucleate Boilina Correlation, TV Electric Company, RXE-88-102-P, January,1989
- 2. Huan B. Giap and David W. Hiltbrand, TUE-1 DNB Correlation SuDDlement 1, TU Electric Company, RXE-88-102-P, Sup.1 December,1990
- 3. Yi-Xing Sung and Huan B. Giap, VIPRE-01 Core Thermal Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensino ADDlications, TV Electric Company, RXE-89-002, June, 1989 10
APPENDIX A Response- to Request for Additional Information on TUE 1 Departure from Nucleate Boiling Correlation
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Log # TXX 91402
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EEEE TEEE i :- :- -File #-10010
--__ .--- 915 illELECTRIC
, = October 30, 1991 Willissa J. Cohm. jf.
Greer ner Pres.dru
.U'. S.' Nuclear Regulatory. Commission-Attn: Document Contro1' Desk Washington, D.--C. 20555 -
SUBJECT:
' COMANCHE' PEAK STEAM ELECTRIC STATION (CPSES)-UNIT 1 DOCKET NO. 50-445-REQUEST FOR ADDITIONAL INFORMATION ON RXE 88 102-
"TUE 1 DEPARTURE FROM NUCLEATE- BOILING CORRELATION" ,
REF: . Letter f rom the-NRC to Mr. William J.- Cahill, Jr. dated October 4. 199.1, Requesting Additional.Information regarding >
. Topical. Report IXE 88 102 Gentlemen:-
Attached..please find 1TU Electric's response to the list of questions provided in the referenced letter.
Should clarification or additional information regarding responses to-the
- . referenced letter be required to enable the Staff to complete its review, contact Mr.-Jimmy 0. Seawright at 214/812 4375.
- Sincerely, William J. Cahill. Jr. r By: 4
, D. R. Woodlan ;
Docket Licensing Manager
'HC P / gj .
Attachment:
c' Mr.=R. D. Hartin. Region IV Resident Inspectors. CPSES (2)
, Mr. T.1AT-Bergman. NRR i: .
. , 4 u. uc ts;,sf .:,bi[i;IO D d F '
400 H. Clive Suwt t.B. I1 - Ddlu Tou mot E - ___ _ . . ,
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M Attac:mant to 00(-91402 Page' 1,of 16 Resperse to NRC Request
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fer Additional Infcrration en RXE-88-102-P l
- 1. NPC Pm uest: he nu: er of experimental data points, 934, was "htlated fer the effects of array size, axial heat flux distribution, grid pitch, heated length, and guide tubes. mis translates to about 187 data points per effect. To cx2:pleta the review of the ET D3 ccrrelation ard ermparisors with other ex:rrelations, please hhilate the nmMr of data points
%@-ding to the varicus pressure levels and rass f uxes l investigated during the testirg.
- TJ Elect ~ic Fescense: Four discreta pe levels can be
. identified within the experitental data base used to develop the ET-1 DB Ccrrelation. Se rarges of these pressure levels arxi the respeed.ve number of data points within each range are:-
. Pressure Pance # of Data reints within rame 1485 - 1565 psia 208 1785 - 1825 psia 176 2045 - 2205 psia 281 2365 - 2435 psia 269 he rass flux range over which the ccrrelation su developed is not as cenveniently discretired as the pressure range. As Figure 5-2 in FAT-BS-102-P.-shows, the local rass flux is relatively centinuously distributed over the endre rarge. However, to facilitata an meca-nt ef; the adequacy of the n -Mr of data t points fcr a sdset of the rass flux range, the follo#ag local <
rass flux levels,. alorg with the nu=ber of data points in each-1evel, have been selected:
-Mass Flux Rame # cf Data ceints within ranag 0.90 - 1.60 Mitm/hr-ft2 172 306
'1.60 - 2.25 Mlbm/hr-ft2 2.25 - 2.70 M11m/hr-ft2 187 269 2.70 - 3.53 Mitn/hr-ft2
- 2. NRC P.ecuest: 2e is=r,;1ature given en page 2-4 identifies Z o as "the boilirg length." In the literature, boiling length refers to the pcrtion of the heated length that is experiencirg boiling corditiens, while ET has chosen this parameter to be the distance fr::n the-inlet to the heated secticn to the point where boiling
Attachoent to TAN.-91402 Page 2 of 16 first m m . Please clarify that this parareter, khich reflects the subcooled lemth, has been prgerly used in the devolgrent ard use of the ccrrelation.
W Elect-ic Pescerse: he parareter 23, in the ncn-unifcrm axial heat flux facter, the s*W Tcng facter, does irdeed represent the subccoled length cf a channel, me use of the sn+mled length as the lower limit in the integral in the Torg facter is corsistent with the develgrant of the Targ facter as described in Beference 3 of RXE-88-102-P. It has teen v uuctly applird in both the develgrent and the snWW use of the 'IUE-1 Dra ccrrelation.
- 3. NRC Recuest: To rake the table on page 2-5 (of RXE-68-102) c:xplete, please identify the rarges fcr the folicwing parareters:
- 1) fuel red diareter, 2) thimble guide tubo diareter, 3) red pite,
- 4) distance frcn inlet at stich OtB ed, and 5) enthalpy at the Eta locatien. Please also sqply the inlet tc=perature for the tests.
'IU Electic Festerse: 'Ihe rarges fer ita 1 through 4 requested alzve are:
niel Rod Diareter: 0.374 - 0.422 inches
'Ihi=ble Guide Tube Diareter: 0.482 - 0.544 indes Rod Pitch: 0.496 - 0.555 inches Distance to Dtm: 68 - 168 inches t e range of the distance to Dta over stich the ccrrelaticn is ccrsidered atplicable is net limited to distances greater than 68 inches even thcogn this represents the icwer limit of the experi:: ental data used in the ccrrelaticn develepocnt. As Figure 1 (attached) shcus, the behavicr of the calculated MCtER exhibits no trend with chargirq distarces to DtE. 'Ihis behavior indicates that extrapolation telcw the 68" value is acceptable.
'Ihe range fcr the enthalpy at the EtG location is not identified.
Se equivalent fluid se y cstich accounts for the effect of the local fluid energy on Dts and %tich is used direedy as inprt irrto the WE-1 htien is the local quality. m e 1ccal qmlity is used to establish the rarge of fluid energies over which the correlaticn can be corsidered valid, he rarse of the 1ccal quality is provided en page 2-5 of RXE-88-102-P.
Similarly, a para.eter which reflects the inlet te=parature and which represents the effect of inlet te=perature en DtB is the inlet fluid energy with respec*. to saturation ccrditicrs. Fcr tPis reason, the rarse of inlet subcooliry in tem of Btu /lin is rcre a m.eiate fer definirq a limitirq rarge. 'Ihe rarge of the inlet suh=clire is given on page 2-5 of RXE-S8-102-P.
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Attact=cnt to TXX-91402 Pace 3 of 16
- 4. I m Recuest: To allow fer a rcre cuantitative reasure of the bias, please prende fits of CQs prcdicted as a fencticn of Qcts ws:rsd fcr each test section and fcr all data ccubined, me intercept cf the . fits should have the value 0.0, with a slope of 1.0.
W Elec~ic Festxrs.s: 2e fits of CDs predicted as a functicn of CQG reasured for all data cmbined and for each test sec-Jcn iniivirbily have teen perfcr::ni using linear regression, me results of the linear regression fits are sumarired in Table 1.
Plots of predictad GF versus reasurud heat flux for all test data cccbined and for each test section are previded in Figures 2 throx:h 21. T o lines are sho.n en each plot. t e tcp line represents the locus of points msgding to a ICtER of 1.16, which is the 95/95 limit fcr the WE-1 Eta ccrrelaticn. Se other line regT.sants the locus of points ccW.m to a MDtER of 1.0.
- 5. NRC Frcuest: to mulation dces not extrapolate outside the ranges of the experi:: ental data base, and under certain ceniitions the mlation predicts necptive values of the EtB heat flux. In view cf these cencerrs, please describe the centrols in tra VIFFI-01 code to ebl with such circu= stances ard also explain stat is done sten the VIFFI-01 calculated ccnditiers exceed any of the experirental data Fw rarges, including the ccrrelation and the Tcng F-facter.
"U Elect-ic Fesvrse: 2e VIFRE-01 code will ter= irate with a fatal er:cr ressage if a negative critical heat flux is calculated. Bere are no centrols within VIFRE-01 to flag % ten calculated canditiers ray be outside the range of applicability of the ccrrelation. It is the respersibility cf the use:r to ersure that the ccrrelation has not been used outside its range of applicability. Ehould any of the calculated coniitiens ey* the rarse of the WE-1 htien, EtG would te assured to cccur.
- 6. NRC Fecuest: Is there any intent to apply the WE-1 m1ation to fuel asserblies that have been reccrstit:.:*d to 1.T lude one or rcre durcy fuel rods? If so, define the configuration limits for such a;plications and jur.ify the applicability of the experirental data base.
W Elec~ic Fesocrse: 2e WE-1 e uulation is ccrsidered to te I applicable to reccrstituted fuel nemblies with the limitation that the WE-1 ccrrelation cannot be applied to reds stich rAare a sirgle subchannel with two er rcre " cold" rods. (" Cold" reds are either guide thirble tubes, irst:unent thirble t %, or reccrstituted fuel reds.) This limitation is n.wmq because the
9 Attac: rent to TXX-91402 Page 4 of 16 experirental data base does not include any test sections sttich similate this ccnfiguration. En test sections in the ET-1 ccrrelation data base sere designed to repw Westirghcuse 1L9(15 and 17X17 fuel ames-nlies. Scce of the test secticrs inc1MM an unheated red to si::ulata a gtide thl=ble tube er an insert =ent thi=ble tube. A "mld %s11 facecra is included in the ET-1 cx::rrelation to am fcr the Eta tchavicr of a heated red which shares a subchannel with an urheated red as exhibited in the tests. me cold wall effect of a reconstiti:ted fuel red is considered to te cccparable to the cold wall effect of the thl=ble mM. m erefore, as long as the configuration of the recanstituted fuel anwhlies does not irx:1ude t.o or rcre unheatcd reds sharing a sirgle sulxtannel, the experirental data base is cosidered to be represen;ative of the fuel assccbly and the ET-1 mlation is applicable.
Attac:=ent to TXX-91402 Page -5 of 16 1
TABIZ 1.
TEST }E BER FIGURE SICPE STD. Y SID.
SECTICN OF DAIA NUMBER DGOR Uf1 E EPT m
!EdIR pontis '5" OF '5" "b" CF "b" R*2 AIL 934 2 0.92521 0.00802 0.04022 0.00487 0.93458 12 4 34 3 0.49569 0.07041 0.45141 0.06345 0.60764 125 33 4 0.56143 0.08606 0.43789 0.08299 0.57857 127 37 5 0.60838 0.10133 0.30744 0.09199 0,50739 131 37 6 0.86961 0.06641 0.05932 0.03167 0.83048 132 36 7 0.81511 0.07668 0.05845 0.03540 0.76778 134 38 8 1.09186 0.05874 -0.04428 0.02714 0.90565 13 9 38 9 0.93280 0.06286 0.03141 0.02953 0.85950 140 32 10 0.64434 0.08522 0.26891 0.07300 0.65581 146 38 11 0.82746 0.07195 0.07832 0.03593 0.78605 148 69 12 0.95622 0.03573 0.02506 0.01723 0.91445 153 41 13 1.17559 0.08458 -0.06700 0.04113 0.S3202 157 78 14 0.85608 0.03555 0.09511 0.02252 0.88412 158 66 15 0.67323 .0.04017 0.18308 0.02656 0.81445 160 66 16 0.65900 0.03852 0.22935 0.02644 0.82058 161 67 17 0.93811 0.05669 0,'2030 0.02554 0.80815 162 68 18 0.97977 0.02625 0.',2125 0.01277 0.95477 163 41 19 0.63544 0.07604 0.23757 0.04933 0.64162 164 69 20 0.99791 0.03054 0.00781 0.01385 0.94094 166 46 21 0.99344 0.08582 0.01251 0.04309 0.75283
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weesured Heat Flus (uBtu/hr-f t2)
r C
f-Attach cnt; to TXX-91402 Page 7 of 16 FIGURE 3.
re., se. io, i 2 4 1.2 1.1 -
' ~ / _ q. -
1 m -
- 0.s -
g c c -Og, 8 c-l 4
0.8 -
\
0.7 -
f2 0.6 -
=
0.$ 9 I
- 0.4
/
.e l.
O.1 0.2 -
--l-0.1 '- /
0 --
/ 0.8 1.2 0 0.2 0.4 0.6 1 weesures Heat flus (wBru/hr-f t2)
FIGURE 4.
To.t Section 125 1.2 O_
1.1 -t C Ch .
1- .= uc-%
C -
p 0.9 - w
=
[
2
- 0. 8 -
N 2 0.7 -
m 2
0.6 -
[
0.5 -
I-g 0.4 -
E 0.3 -
O.2 -
0.1 -
0 .
0.8 1 1.2 0 0.2 0.4 0.6 Woosured Heat Flus (WBtv/hr-f t2)
i Attac=nent to DC(-91402 Page 8 of 16 FIGURE 5.
- f. t seceien 127 1.2 i 1.1 C/C
/: l
,C - =
e 3:
g,e e ==
- 0. 6 ,
C ~
2 0.7 3
2
~
0.6 -
]
! lN i - // 1 0.2 !.
0.1 - ,
0 '
0.3 i t, O 0.2 0.4 0.6 u.cswree Heat Flwa (WBtu/nr-f t2)
FIGURE 6.
- r. t s. , ion iai 1.2
! / / i
/-
' ~l g
0.s -l N
0.s1t j' O.7 -
'a U 0.6 - 4 6
/C./D"
{ CA:- :
0.s -
~~f AU I.
f 0. 4 -
~
f3
~
E A 0.3 -
~
- 0. 2 -
0.1 - ?
i 0 ' f.2 i 0.8 1 i
0 0.2 0.4 0.6 Weasur.o Heat flus (u8tu/ne-f t2)
1 Attact::nerm to T.tN-91402 Page 9 of 16 FIGURE 7.
Test Section 132 1.2 /
1.1 1 -
I
^ 0.9 d U.
l 0.8 -
N 2 0.7 =
m 3
- 0 Q.6 -
0.5 m ,
h g 0.4 1 f,C s==
AC0 d o,3
/ 50 0
C 0.2 -
0.1 - ,/
0 ,
0.4 0.6 0.8 1 1.2 0 0.2 Weasures Heat Flwu (W6tu/hr-f t2)
FIGURE 8.
r.., s..tio u4 1.2 -
i 1.1 -
1-
^ 0.9 *
=
[ 0. 8 -
5 2 0.7 -
- 0. 6 -
0.5 - Ca
"# C l
3 0.4 - G-X .
1 55~
E 0'3 I d w 0.2 -l l 0.1 1 /
l 1 0 .
0.8 1.2 O Q.2 0.4 0.6 1 Measured Heat Flus (uBtu/hr-f t2)
}
i e
Attactre.nt *w TXX-91402 Page 10 of 16 FIGURE 9.
7..,s.o.,i39 1.2 s
i.i -
1-g 0.9 -1 1 0. 8 -
k j
2 0.7 - 0 C
0
- 0. 6 - y 0.5 -
04 .
~C E 03 O.2 -
0.1 - ,/
0 ^ 0.8 1 1.2 0.4 0.6 0 0.2 W.osureo Heat Flus (WBlu/hr-f t2)
FIGURE 10.
r..,s.o;. i40 t 1.2 ' /
i.i - /
/
C i-C a C
^ 0.9 - r 2 JQ G.S -
. O N C j
3 0.7 - C
- 0. 6 -
{ll:
0.5 -
0.4 m
-f I
Q- 0.3
- 0.2 -
- 0. , -
0 1.2 0.6 0.5 t 0 0.2 0.4 Wea.ured Heat rius (Meru/hr-f t2)
w Attac :nuit.to TAN. -91402 Page 11 of 16 FIGURE 11.
- t. .t s.. ti., i6 t.:
- 1. 3 - '
1 -
l
]
- C.9 -
l 1
0.8 -
N 2 0.7 -
c
- 0. 6 - 0,l d
l 0,5 -l . N U
W j 0.4 -
ff3 _
' O.s -
0.2 - ,
0.1 ~ /
/
0 0.4 0.6 0.8 1 1.:
0 0.2 W.osur.a H.at Fluu (W8tu/M-f t2)
FIGURE 12.
r..t s. tion i4e 1.2
,/
1.1 -
/
i-p 0.9 -
l 0.8 -
f
=
0 2 0.7 -
0.6 -
! Il!-
0.24 0.1 - !
[
=
0 ,
0.8 1.2 0 0.2 0.4 0.6 1 weasureo Hot Fium s'uBlu/Mr-3f 2)
%j %
1 Atta h to TXX-91402 Page 12 of 16 FIGURE 13. ,
l Test Section 153 1.2 .
,., - 1 1 -
/
E c/
"] /c Iq 0.3 -
3 0.7 -
a 0.6 -
N y ,. -/
v g CE,4
'I OD O W 4C L 0.3 -
0.2 -
0.1 -
. ./
/
0" 0.6 0.5 1 1.2 0 0.2 0.4 u...or.. ..t no, G 0.5 -
g 0.4 - -
o L
I 0.3 -
0.2 -
i 0.1 - ,
0 0.8 f.:
0 0.2 0.4 0.6 1 we.swred Heat flus (uBtw/hr-f t2)
o .
1 .,
e <
e.
Attac:=e.nt to TXX-91402 Page 13 of 16 FIGURE 15.
re.t section i 8 1.2 .,
1.1 -
1-
^ 0.9 - /
2 /
T 6 0.8 , A* -
0.7 o Z 5' ze &C 3 e ac 0 n,S a 8; Y
- C C 2
0.4 u l 4 % ~ _~
E 0.3
- 0. 2 -
1 0.1 d /
0 ,
0 0.2 0.4 0.6 0.8 1 1.2 Weasurea Heat rius (wBlu/hr-f t2) ,
FIGURE 16.
Test Section 160 i.: _
1.1 d 1 *
^ 0.9 - C
~ pon *
[ 0.8 -
. _., O
- k e-# D 3 0.7 - CCYGa~ ~
$ o # *
[ 0.6 - c p C ,
- 0. 5 - -[ b y 0.4 -
' O.3 -
0.2 -
0.1 - /
0 0 0.2 0.4 0.6 0.8 i t.2 weasures Heat rius (wBtu/ne-f t2)
o .
. e. .
4 Attach:aent to TXX-91402 Page 14 of 16 FIGURE 17.
Test Section 161 1.2 ,
l 1.1 -
1-p 0.9 -
0.8 -
1 0.7 -
m-2 0.6 - .
h 4 l
0.S 1 ,f l s' 04 (s
t , *_
4 ,
~~ "
A 0.3 -
0.2 -
0.1 - /
e 0.4 0.6 0.8 1 1.2 0 0.2 Woosuroc Heat flua (W0tu/pr-f t2)
FIGURE 18.
Test Section 162 1.2 1.1 -
t-g 0.9 -
[ 0.5 -
t C 2 0.7
- r0 D
- 0. 6 -
E A ,e -
v w g,3 ,
0 1
- 0. 4 - E e
5 0.3 - -
0 0.2 -
0.1 ;
}
i .
0 0.6 0.5 1 1.2
. 0 0.2 0.4 Woosured Hoot Flus (W9tu/hr-f t2)
s e.
Attac: rent to TXX-91402 Page 15 of 16 FIGURE 19.
t.., s o. t .. i63 1.2 1.1 w '
1 .
q
- 0. 9 -
0.8 4
\
Sh m0 2 0.1 ~ ,f"c CV d i v = c.o s
0.6 -l a ce_
p'IT
~
U 0,3 , N 1
f 0. 4 -
I
/
/*
i E 0.3 J' 0.2 ~l , /
l '
/
0.1 ~ ,'
0 0 0.2 0.4 0.6 0.8 1 1.2
. Woosures Hoot rius (wBtw/ht-f t2)
FIGURE 20.
eest Section 164 1.2 ,
i.i-I
/ /1
/
/
i.
g 0.9 -
/
1 0. 8 -
z N
2 0.1 =
$ 0 CDC
- 0. 6 - go U [
- a tt:
0 0,3 C4 -
- e ,.c -
e -
5 v 0. 4 - N+
C/- w 5'
O.3 - -
0.2 - p 0.1 -
0 ^
0 0.2 0.4 0.6 0.8 1 1.2 weesures Meet riwi (wBiw/me-'t2)
o*
Attsctr:ent to TXX-91402 Fogo 16 of 16 FIGURE 21.
v . . . s . . ,4. . isi t.2 ,
1.1 -
1 -
I g 0.9 d
- o f 08 -
0.7 0.6
- i mh 0
[
2 4
S*
7 i ] 8 0 0.e N rh 5 3.3 -
0.2 -
0.1 * /
0 0.2 0.4 0.6 0.C 1 1.2 weesures west fles (w8tw/hr-f 92) ,
__ - - - - - - -