ML20067B129

Suppl 1 to TUE-1 DNB Correlation

ML20067B129
Person / Time
Site:	Comanche Peak
Issue date:	12/24/1990
From:	Husain A, Maier S TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20067B123	List: ML20067B119 ML20067B129
References
RXE-88-102-NP, RXE-88-102-NP-S01, RXE-88-102-NP-S1, NUDOCS 9102080142
Download: ML20067B129 (31)

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[ TUE 1 DNB CORRELATION SUPPLEMENT 1 December 1990

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liuan B. Giap David W. Ill! tbrand Reviewed: '

Date: /l!2/!90 Stephen M. Maier Supervisor, Transient Analysis 9

l2)2f/ /90 Approved: Date:

Ausaf Husain Director, Reactor Engineering

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I I DISCLAIMER The information contained in this report was prepared for the specific requirement of Texas Utilities Electric Compmy (TUEC), and may not be appropriate for use in situationi, other than those for which it was specifically prepared. TUEC PROVIDES NO WARRANTY llEREUNDER, EXPRESS OR IMPLIED, OR STATUTORY, OF ANY KIND WilATSOEVER, RECARDING TilIS REPORT OR ITS USE, INCLUDING BUT NOT LIMITED TO A'JY WARRANTIES ON HERCllANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE.

I By making this aport available, TUEC does not authorize its use by others, and

( any such use is forbidden except with.the prior written approval of TUEC. Any such written approval shall itself be deemed to a Tcorporate the disclaimers of

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liability and disclaimers of warranties provided herein. In no event shall TUEC have any liability for any incidental or consequential damages of any type in connection with the use, authorized or unauthorized, of this report or the i

information in it.

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l ABSTRACT I A study has been performed to extend the application of the TUE-1 Departure from Nucleate Boiling (DNB) correlation to ( ), The TUE 1 DNB correlation was developed at TU Electric using the Columbia University DNB data base, VIPRE-01 thermal hydraulic code, and the Statistical Analysis Eystem. The original data base for the TUE-1 correlation consisted of 934 data

.I points representative of Westinghouse 15x15 and 17x17 fuel with R-type mixing vane grids. In this supplement, DNB test data representative of ( )

were analyzed to validate the TUE-1 correlation for use-with (

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I TABLE OF CONTENTS T

PACE ABSTRACT........................................ .............. iii TABLE OF C0NTENTS.............................................. iv L?ST OF TABLES.......................................... ...... VI LIST OF FICURES................................................ Vil

1. INTRODUCTION............................... .....................-1-1 1.1 Purpose.............. ..................................... 1-1 1.2 Intended Applications................................... 1-2 I

1.3 Methodology ............................................... 12

2. [ ] DATA BASE................................... . ........ . 2-1 2.1 Data Selection. ...................... .... .............. 21 2.2 Data Elimination.......................................... 2-1 l 3. MDNBR Calculations'... ......................................... 3-1 3.1 Computer Code............... .............................. 3-1 3.2 VIPRE 01 Subchannel Mode 1....................... ......... 31 l

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4. STATISTICAL EVALUATION.,.................. .................... 4-1 l

4.1 [ ] Data................................................. 4-1 l

4.2 ', l.............. 4-1

! 4.3 Data Plots................................................ 4 2 4.4 95/95 DNBR Limit for the Expanded TU E 1 D a t a B a s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2

5. CONCLUSION................................................,.... 51 1

1 6. REFERENCES..................................................... 6-1 I

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I g-I TABLE OF CONTENTS (continued) j APPENDICES PACE A. [ J DNB Da t a S ununa ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A 1 I

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LIST OF TABLES l

I TABLE PAGE I ] Data and the Original 23 21 Comparison of the [ Data..............

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g-I I LIST OF FIGURES I

FIGURE PAGE I 21 Test Assembly Geometry and Radial Power Distribution... ......... 2-4 I 3-1 Axial Noding Configuration for [ ] Data.............. . ..... 32 I 32 Channel and Rod Layout for [. ] Data................. .... .... 33 I

41 Predicted DNB Heat Flux vs Local Heat Flux for [ ] Data........ 45 42 Predicted DNB Heat Flux vs Local Heat F'.ux for Expanded Data Set. 4-6 43 MDNBR vs System Pressure........................ ...... .... . 4-7 t

i 4-4 MDNBR vs Local Quality.............. ............................ 4-8 I 45 HDNBR vs Local Mass Flux...,........................... ......... 4-9 I

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CHAPTER 1 i

INTRODUCIION

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1,1 Purnose I <

I ) This supplement describes the analysis of additional experimental DNB test data which

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4 l 1 TU Electric presented the TUE 1 DNB correlation in Reference 1. The original TUE-1 correlation data base consisted of 934 experimental data points representative of Westinghouse 15x15 and 17x17 R-grid fuel. The TUE-1 DNB cort 4 lon 95/95 DNBR limit was evaluated to be 1.16, based on statistical

analyses of the experimental data predictions. [

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i I-1.2 Intrnded Applications TU Electric intends to employ the TUE 1 DNB correlation for licensing and safety calculations using the VIPRE 01 thermal hydraulic code (Reference 7),

The applications of the TUE 1 correlation will include DNB related cale.11ations required for core safety liinit curve calculations, reactor protection system  ;

setpoint analysis, and safety analyses for normal operation and DNB-limited I events.

I 1.3 Methodninny A VIPRE 01 thermal-hydraulic model represented the [ ] fuel which was used to obtain the DNB data. This model is consistent with the model used in the analysis of the original correlation data base. The TUE 1 Minimum l .

Departure from Hucleate Rolling Eatio (HDNBR) predictions for the new data were examined using several statistical tests. First, the ( ) data base was tested for normality using the D' test. Then, statistical combinability tests were performed to (

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). The following statistical analyses were then performed on the expanded correlatian data base, which consists of the original data and ,

the additional [ ):

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1) The expanded dcta base was tested for norraality using the D' test, j I 2) Statistical combinability tests were performed to determine [

I ). Subgroups that were tested included uniform and nonuniform axini heat flux profiles, bundle arrays (15x15 or 17x17), heated lengths, subchannel hydraulic diameters, grid spacing, subchannel-types (typical and thimble cells), and fuel rod diameters.

3) . Scatter plots of predicted MDNBR versus independent variables (such as heat flux, local quality, and pressure) were examined to determine if the correlation is biased over the range of any independent variable.

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4) The 95/95 DNBR limit for the expanded data base was-calculated using the Owen's one sided tolerance factor.

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CHAPTER 2 I [ ] DATA BASE .

2.1 Data Selection The data selected for this evaluation are from the (

). This test section has a configuratior.. representative of

[ ] fuel assembly with a ( ) inch fuel rod outside diameter The [ ] test section data base consists of [ ] data points. The characteristics of the [ ] test section and the range of experimental operating conditions are shown in Table 2-1. For comparison, the range of operating conditions for the original experimental data used to develop the I TUE-1 DNB correlation is also shown in Table 2-1.

y I F.Sure 2-1 shows the channel and rod layout for test section [- ) with radial power factors. ,

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?.2 Data Elimination I One data point was excluded from the analysis because it was evaluated to be a statistical' outlier. This exclusion is based on the same data elimination I

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technique, Chauvenet's Criterion, that was applied to the original experimental data base. Chauvenet's Criterion is discussed in detail in Reference 1.

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TABLE 2-1 Comparison of the [ ] Data and the Original Data .

[ ] Data Original Data Test Section i )

Pressure (psia) 1485 to 2435 Inlet Mass Flux 0.93 to 3,53 (Mlbm/hr ft2)

Local Quality -0,15 to 0,30 Local Heat Flux 0,14 to 1.15 (MBTU/hr ft2)

Inlet Subcooling 30 to 350 (Btu /lbm) i Mi *ng Vane Grid 20 to 32 Spacing (in) i lleated Length (in) 96 to 168 Rod Diameter (ir) 0.374 to 0.422 Vetted liydraulic Equivalent Dia (in) 0.37 to 0,51 lleated llydraulic Equivalent Dia (in) 0.46 to 0.58-Axial lleat Flux uniform, cos(u), (u) sin (u)

Assembly-Average I Grid Loss Coef 1.20 to 1,90 I

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FIGURE 2-1 Test Assembly Geometry and Radial Power Distribution I '

NOTE: The decimal nwnbers inside the rods' denote the radial power factor and the intager numbers inside the rods denote the rod number.

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l MDNBR CALCULATIONS I 3.1 Computer Code i

The VIPRE 01 computer code (Reference 7), nodified to include the TUE-1 DNB a correlation, was used to predict the thermal-hydraulic conditions and MDNBR for the analysis of the test data. .

3.2 VIPRE 01 Subchannel Model ,

The thermal hydraulic codel for the [ ] test section is consistent with the model used in developing the itJE 1 coccelation (Reference 1). Similar to the thermal-hydraulic model sr.d for t he 'TUE-1 correlation development, the model for the ( ) test section is a full model of the whole test section; all 36.

nubchannels and all 25 rods (24 heated and 1' unheated) are explicitly modeled.

The axial noding scheme procides for finer cash spacing in the regions where the MDNBR occurs. Figures 3-1 and 3 2 show the axial noding and the channel and rod layout used for the VIPRE-01 model, I

A conservative ABETA value of 0,02, as recommcnded by EPRI (Refedance 6), is used for the turbulent crossflow mixing coefficient, 3-1 l

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I FIGURE 3-1 Axial Noding Configurat. ion for (- ] Data I

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Rod number 1 2 3 4 5 6 (1 2 3 4 h

5 7 8 9 10 11 12 f 16 17 18 19 6 13 14 15 16 17 18

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I 25 26 27 28 29 30 13 12 11 10 9 31 L 32 33 34 35

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FIGURE 3-2 channel and Rod Layout for [

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g-I CHAPTER 4 I

STATISTICAL EVALUATION I 4.1 [ ]. Data I A listing of the calculated MDNBRs and corresponding local conditions for each

[ ] data point is provided in Appendix A. By application of the D' test (Reference 3), the data was determined to be normally distributed. The mean~and standard deviation for the MDNBR predictions were evaluated to be [ ] and

[ ], respectively.

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I ] The F test and t-test _(Reference 4) were used to test the equality of the variance and the mean, respectively, consistent with the methods used in Reference 1. [

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I The results of the comparison are shown in Table 4-1, [

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I 4.3 Data Plots I

To determine if the correlation describes the DNB phenomenon for the-expanded data set accurately and without any bias,-scatter plots are examined, Scatter plots of predicted DNB heat flux vs local heat flux and of predicted MDNBR 1

versus system pressure, local quality, and local mass flux are shown in lI l Figures 4-1, 4 2, 4 3, and 4-4, respectively. Visual examination of these plots shows that (

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4,4 95/95 DNBR Jimit for the Expanded TUE 1 Data Base I

The 95/95 DNBR limit for the expanded TUE-1 data base is calculated as follows:

(1) The D' test (Reference 3 is used to test the expanded data set ior normality.

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I (ii) A nean and sts.ndard deviation of [ ), respectively, are calculsted for the expanded data base, Because the data base is normally distributed, Owen's one sided tolerance limit factor (Reference 5) is used to calculate the 95/95 DNBR limit, as shown below.

I 95/95 DNBR Limit - m + s

• K(n,95%,95%)

where: m is the sample mean s is the sample standard deviation K(n,95%,95%) is the Owen's one-sided tolerance 15.it factor for calculating a 95/95 limit for a sample set of f

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!I The Owen's factor for a sample size of-[

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I FiB ure 4 1 Predicted DNB Heat Flux s Local Heat Flux p for (- ) Data 5.

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Figure 4-2 Predicted DNB fleat Flux vc Local lleat Flux for Expanded Da':a Set I

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Figure 4 5 MnNBR vs Local Mass Flux 49

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I CHAPTER 5 CONCLUSION

I This supplement provides the justification for the use of the TUE 1 DNB correlation for [ ] fuel assemblies. The methodology employed one DNB test section of [ ]

and the subchannel 4.nalysis computer code VIPRE-01. The thermal hydraulic model for this test section is consistent with the model used in the analysis of the I

original data. Statistical analyses [

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CllAPTER 6 REFERENCES I

I 1. RXE 88-102 P, Rev.0, "TUE 1 Departure from Nucleate Boiling Correlation",

January 1989.

2. [

3. ANSI N15.15-1974, "American National Standard Assessment of the Assumption I of Normality (Employing Individual Observed Values)".

4. Bernard Ostle rad Richard Mensing, " Statistics in Research", 3rd ed., Iowa State University Press, 1982.

5. SCR-607, D.B. Owen, " Factor for One-Sided Tolerance Limits and for Variables Sampling Plans", Sandia National Laboratory, 1958.

6. EPRI-NP-2609, " Parametric Study of CliF Data", Vol.2, " Generalized Subchannel CllF Correlation-for PWR and BWR Fuel Assemblies", Page 2 38, Project 813, Jan. 1983.

7. EPRI NP-2511-CCM, Rev.2, "VIPRE 01: A Thermal-Flydraulic Code for Reactor Cores'., July 1985.

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I APPENDIX A

[ } DNB DATA

SUMMARY

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