ML20078C159
| ML20078C159 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 01/13/1995 |
| From: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Borchardt R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19311B676 | List: |
| References | |
| AW-95-773, NUDOCS 9501260203 | |
| Download: ML20078C159 (104) | |
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Westinghouse Energy Systems Ba 355 Electric Corporation Pinsburgh Pennsylvania 15230-0355 AW-95-773 January 13,1995 i
Document Control Desk
.j IJ.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION:
MR. R. W. BORCHARDT APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
SUBJECT:
PRESENTATION MATERIALS FROM THE DECEMBER 20,1994 MEETING ON AP600 TEST AND ANALYSIS PROGRAM
Dear Mr. Borchardt:
The application for withholding is submitted by Westinghouse Electric Corporation (" Westinghouse")
pursuant to the provisions of paragraph (b)(1) of Section 2.790 of the Commission's regulations. It contains commercial strategic information proprietary to Westinghouse and customarily held in confidence.
The proprietary material for which withholding is being requested is identified in the proprietary version of the subject report. In conformance with 10CFR Section 2.790, Affidavit AW-95-773 accompanies this application for tvithholding setting forth the basis on which the identified proprietary information may be withheld from public disclosure.
Accordingly, it is respectfully requested that the subject information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations.
Correspondence with respect to this application for withholding or the accompanying affidavit should reference AW-95-773 and should be addressed to the undersigned.
Very truly yours, Dx //
A N. J. Liparulo, Manager Nuclear Safety Regulatory And Licensing Activities
/nja cc:
Kevin Bohrer NRC 12H5 9501260203 950113 PDR ADOCK 05200003
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1
. AW-95-773 AFFIDAVIT COMMONWEALTil OF PENNSYLVANIA:
ss COUNTY OF ALLEGHENY:
l Before me, the undersigned authority, personally appeared Brian A. McIntyre, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth i
in this Affidavit are true and correct to the best of his knowledge, information, and belief:
Brian A. McIntyre, Manager Advanced Plant Safety and Licensing Sworn to and subscribed before me this
/7 day of D
.1995 U
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Notary Public tbtatiSaa!
Rose Marie Payne,t&2y PLbhc Monroese BeraJ.irgenyCostf MyCommisoon EmrosIbe.4.1953 Mermer,WWof totanes 2244A
9 AW-95-773 (1)
I am Manager, Advanced Plant Safety & Licensing, in the Advanced Technology Business Area, of the Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Energy Systems Business Unit.
l (2)
I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit.
i (3)
I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Business Unit in designating information as a trade secret, privileged or as I
confidential commercial or financial information.
(4)
Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
l (i)
The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
(ii)
The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold cenain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
l Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
i i
2244A
4 AW-95-773 (a)
The information reveals the distinguishing aspects of a process (or component, I
structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b)
It consists of supporting data, including test data, relative to a process (or l
component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c)
Its use by a ccmpetitor would reduce his expenditure of resources or improve his competitive oosition in the design, manufacture, shipment, installation, l
I assurance of quahiy, or licensing a similar product.
l (d)
It reveals cost or price information, production capacities, budget levels, or commercial strategies of M estinghouse, its customers or suppliers.
(e)
It reveals aspects of past, present, or future Westinghouse or customer funded i
development plans and programs of potential commercial value to Westinghouse.
(f)
It contains patentable ideas, for which patent protection may be desirable, l
i There are sound policy reasons behind the Westinghouse system which include the I
following:
(a)
The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from l
l disclosure to protect the Westinghouse competitive position.
l l
l (b)
It is information which is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to l
sell products and services involving the use of the information.
22444 l
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9 AW-95-773 (c)
Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
i (d)
Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive r
advantage. If competitors acquire components of proprietary information, any I
one component may be the key to the entire puzzle, thereby depriving i
Westinghouse of a competitive advantage.
9 (e) linrestricted disclosure would jeopardize the position of prominence of l
Westinghouse in the world market, and thereby give a market advantage to the i
competition of those countries.
j (f)
The Westinghouse capacity to invest corporate assets in research and :
development depends upon the success in obtaining and maintaining a competitive advantage.
Ij (iii)
The information is being transmitted to the Commission in confidence and, under the i
provisions of 10CFR Section 2.790, it is to be received in confidence by the' Commission.
i i
i (iv)
The information sought to be protected is not available in public sources or available l
l information has not been previously employed in the same original manner or method i
to the best of our knowledge and belief.
(v)
Enclosed is Letter NTD-NRC-95-4387, January 13,1995 being transmitted by Westinghouse Electric Corporation (W) letter and Application for Withholding Proprietary Information from Public Disclosure, N. J. Liparulo (E, to Mr. R. W. Borchardt, Office of NRR. The proprietary information as submitted for use by Westinghouse Electric Corporation is in response to questions concerning the AP600 plant and the associated design certification application and is expected to be applicable in other licensee submittals in response to certain NRC requirements for justification of licensing advanced nuclear power plant designs.
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AW-95-773 i
This information is part of that which will enable Westinghouse to:
i l
l (a)
Demonstrate the design and safety of the AP600 Passive Safety Systems.
(b)
Establish applicable verification testing methods.
(c)
Design Advanced Nuclear Power Plants that meet NRC requirements.
l (d)
Establish technical and licensing approaches for the AP600 that will ultimately result in a certified design.
(e)
Assist customers in obtaining NRC approval for future plants.
Further this information has substantial commercial value as follows:
l (a)
Westinghouse plans to sell the use of similar information to its customers for purposes of meeting NRC requirements for advanced plant licenses.
(b)
Westinghouse can sell support and defense of the technology to its customers in the licensing process.
l Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar advanced nuclear power designs and licensing defense j
services for commercial power reactors without commensurate expenses. Also, public j
disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the infonnation.
l The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort l
and the expenditure of a considerable sum of money.
i l
l 7244A
l t
l AW-95-773.
In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended for developing -
analytical methods and receiving NRC approval for those methods.
Further the deponent sayeth not.
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l 2244A
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! to Westinghouse Letter NTD-NRC-95-4387 l
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2243A
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L2 Agenda Butler (8:30 - 8:45)
Introduction Butler (8:45 - 9:00)
Review of Test Analysis / Code Validation Schedule and a
Progress Analysis Document Overviews CMT Final Data Report Rarig (9:00)
CMT Test Analysis Report Hochreiter (9:15)
Haberstroh 1
Wright NOTRUMP CMT Preliminary Validation Report Hochreiter (10:15)
NOTRUMP Code Applicability Document Kemper (11:00)
All Round Table Discussions AP600 Test Analysis / Code Validation Report Content (12:30)
(Report Outlines, Technical Content)
Review Schedules (AP600, WCOBRA/ TRAC)
(1:30)
All (2:30 - 3:00)
Meeting Wrap-up & Action items
V1 Westinghouse Electric Corporation
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i Westinghouse /NRC Meeting i
AP600 Test & Analysis Reports I
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December 20,1994 Monroeville, PA i
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S TEST PROGRAM STATUS
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i ALL DESIGN CERTIFICATION TESTS ARE COMPLETE Passive Containment Cooling System Testing Testing Completed Final Test Reports Submitted Core Makeup Tank Testing Testing Completed Final Test Report Submitted SPES-2 Integral Systems Testing Testing Completed (Completed 10/10/94)
All Category 1 and 2 Quick Look Reports Submitted OSU Integral Systems Testing Testing Completed l
All Category 1 and 2 Quick Look Reports Submitted 1
ADS Phase B Testing Testing Completed (Completed 11/11/94)
Test Reports in Progress
y!!!"'-lig TEST PROGRAM STATUS v
TEST RUNS 100
. 90. 91 90
- 87 90 91 91 91 91 88 86 r/>
80 g2 h
70
- 70 74 5
60
.,a 55
- .u Vi
'54 s
4tt 40 d
40 TEST PROGRAM COMPLETED H
30 O
2ey 26 H
20 W
16 II 10 I
i O
+-
J AN (94) h1AR h1AY JUL SEP NOV J AN (95)
MAR MAY FEB APR JUN AUG OCT DEC FEB APP TIME Program Plan Objective (ugxlated)
Actual Test Run Status (through I!/30/94)
Includes CMT, OSU, SPES-2, and ADS Tests i
i
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TEST PROGRAM STATLLS QUICK LOOK RGPORTS 40 m
38 38 18 37 35 V
35 O
A 33 33 30
+
=
30 30 y
(through 12/7/94)
=
23 20 22 M
19
=
9 17 D
14
=
O 10 12
=
q w
=
F-7 7
7 O
4 4
4 F-0 J AN (94) h1AR h1AY JUL SEP NOV J AN (95) h1AR hlAY FEB APR JUN AUG OCT DEC FEB APR TIME Program Plan Objective Actual QLR Status (through 12/7/94) includes Ch1T, OSU, SPES-2, ADS, and PCCS Tests
gli"~ly i
TEST ANALYSIS STATUS l
35 31 29 29 29 29
=
30
=
m HM 25 O
21 c
h 20 A
16 O
g 15 I
11 11 10
=
10
=
6
- 8 55 5
3 i
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AUG 94 OCT DEC FEB APR JUN AUG SEP NOV JAN 95 MAR MAY J UI.
Slip 95 TIME Project Plan Schedule (9-1-94)
Actual Report Status (through Il-30-94) e
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i l11""l1 LL TEST ANALYSIS STATUS mea em-.__
Areoo ANALVStB StPORIS COMPL E leuN DOCUAdfMI sus PAIE NUMDtn asONiel Olm pATE FflOJECI TEST DESGSFIIgpg 83384 ha AUG 94 e 30 94 NOIMMP OSU NOIRtMP Uppeede Ageewt OSU Hee Pee Op f eet Reeute (6 eenoeg 64P PASIDUE 93094 OSU tenee OSu Seenne Repe,e 9 it M WCAP14Isi 93094 WCJI WCfI Code Appapetjay Deemoeient OCE 10 38 94 WCAP84190 PCS See SASM - see ee.en #2 10 39 94 PCSusRtam lo to M to IF M Meee leonese Beem 10 31 94 M109 bSee 001 1030 M NOIRtMP CMT NOIRUMP - CMI Peeken Code VeWeseen Repeet NOW il it 94 Wt AP 84/06 11 30 94 NO TRtMP NOIRueAP Code Apphoebety Documeens il 30 94 MlOS USH suo/
ll 30 M LOf1RAN CMI LOf IR AN CMI Peehan Code Vetusseeen Repe,t PASI DUt WCAPt4/e6 t130 M CMf CMi Teet Anstree Repost t 9 30 94 WC AP I4734 9 9 30 M tOfIRAN tOfIRAN Code Appteehesy Desuenene DEC 12 31 M CMI f eieI CMI Seeseeg Report JAN M f19 228M WCJI CMI WCJI CMI Peekn Code VeWeteen Report thitesnes MAR 330 M LOFIRAN SPE S tOf TRAN SPL5 Pesown Code VeWeteen Report 3 30 M OSU OSU Teet Anetree Report 330 M ADS ADS feet Anee ee Report r
3 30 M NOTRtMP ADS NOIRUMP ADS Peeaun Code VeWee en Report APR SPt 5 feet Anstr e Report theceenet 43095 SPE S e
4 30 M (OFIRAN lOFIRAN V&V Report 4 30 M NOIRUMP Sf18 NOthuMP - SPt S Peeten Code VeWeesen Repeat 4 30 M WGO THIC WGOileC WCAP - Rev 9 4 30 M WOO THIC WGOtteC Band Test hedeutemne MAY
& 30 M NOlmMP OSU NOIRUMP OSU PWetuoi Code Veledeteen Meyest 6 30 M WCII OSU41C WCsf - OSU4TC Peeton Code Vehdeteen Report 6 30 M WCif ADS WCil - ADS Peehm Code Vehdessen Repen 6 30 M
$$AR Peenweseery Non LOCA Anotyee 5 30 M SSAR Pt -
581OCA Annoyee 6 30 M WCli OSU WCsi OSU hetan Code Vendeeson Repe.e 6 30 M WCJi 6Pt S WCf f SPtS Peeaan Code Vehdessen Repest t 30 M S$AR Po _ ^ _, & BLOC A Anesyee SEP M 9 30 M WCl3 WCl1 V&V Report 9 30 M NOlettMP NOIRtMP V&V Recent
I yny CMT FINAL DATA REPORT
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i Bruce Rarig AP600 Project Engineering 4
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CMT FINAL DATA REPORT I
AP600 CMT TEST & ANALYSIS PROGRAM DOCUMENT
SUMMARY
CMT SCALING REPORT Identifies phenomena of importance and relationship of phenomena to AP600 postulated 5
accident scenarios l
CMT TEST SPECIFICATION Specifies the CMT Test Matrix I
CMT FACILITY DESCRIPTION REPORT Describes the CMT test facility COLD & HOT PRE-OPERATIONAL TEST Provides the preliminary data for facility i
characterization QUICK LOOK REPORTS MATRIX TEST QUICK LOOK REPORTS Providas the preliminary data for each test series (100,300,400, and 500) 1 CMT TEST DATA REPORT Provides the final CMT test data determined to be acceptable for code development and validation i
4 CMT TEST ANALYSIS REPORT Documents the results of the data analysis i
NOTRUMP (CMT) PRELIMINARY CODE Provides NOTRUMP comparisons to 300-series tests I
VALIDATION REPORT i
LOFTRAN (CMT) PRELIMINARY CODE Provides LOFTRAN comparisons to 500-series tests VALIDATION REPORT 1
- lir, CMT FINAL DATA REPORT
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PHENOMENA IDENTIFICATION AND RANKING TABLE (PIRT) FOR THE AP600 CMT. _..
Phenomena LBLOCA SBLOCA MSLB SGTR 1)
CMT Draining Effect Condensation on cold thick steel surfaces H
H L
L Transient conduction in CMT walls H
H L
L Interfacial condensation on CMT water surface H
H M
M Dynamic effects of steam injection and mixing H
H M
M with CMT liquid and condensate Thermal stratification and mixing of warmer H
H M
M condencate with colder CMT water 2)
CMT recirculation Natural circulation of CMT and CL balance leg L
H H
H Liquid mixing of CL balance leg, condensate, L
H H
H and CMT liquid Flashing effects of hot CMT liquid layer L
H L
L CMT wait heat transfer L
M M
M Low importance L
=
Medium importance M
=
High importance H
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CMT TEST PROGRAM KEY RESULTS 49 TEST RUNS WERE ACCEPTED FOR USE IN CODE DEVELOPMENT AND VALIDATION (DATA ANALYSIS)
EACH TEST RUN WAS EVALUATED FOR " ACCEPTABILITY" USING:
PRE-DEFINED TEST ACCEPTANCE CRITERIA (INIITIAL CONDITIONS, FINAL CONDITIONS, CRITICAL INSTRUMENT OPERABILITY)
A SIMPLIFIED MASS BALANCE CALCULATION A COMPARISON WITH SIMILAR TEST RUNS TO CHECK CONSISTENCY OF CRITICAL FLOW AND LEVEL DATA
girig CMT FINAL DATA REPORT CMT TEST DATA REPORT OUTLINE
SUMMARY
1.0 INTRODUCTION
2.0 TEST FACILITY DESCRIPTION 3.0 TEST ACCEPTANCE 4.0 TEST RESULTS
5.0 CONCLUSION
S
6.0 REFERENCES
APPENDICES A
Data Reduction for CMT Matrix Tests B
Data Acceptance Results C
Failed and Changed instruments D
instrument Error Analysis E
Thermocouple Measurement Bias Corrections F
Data Plots G
Data Files H
Facility Drawings
a e
CMT FINAL DATA REPORT i
CONCLUSION THE " ACCEPTED" TEST RUNS PROVIDE SUFFICIENT DATA TO ASSESS THE KEY THERMAL-HYDRAULIC PHENOMENA IDENTIFIED IN THE PIRT TABLE.
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CMT Test Analysis Report Approach and Methods Bob Haberstroh Nuclear Safety Analysis
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Analysis Ot@ii.ms Develop / verify correlations for the CMT and develop understanding of CMT thermal-hydraulic phenomena to ensure PIRT items are addressed.
i This includes:
Wall Condensation Heat Transfer Selection and Comparison to Correlation Fluid to Wall Convective Heat Transfer Interfactial Heat Transfer and Mixing Depth Recirculation Behavior 1
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TABLE OF CONTENTS i
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Section Title h
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SUMMARY
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1.0 Introduction 1-1 l.1 Background 11 j
1.2 Analysis Objectives 17 j
1.3 CMT Test Matrix l9 2.0 CMT Analysis Methodology 21 l
2.1 Analysis Modeling Introduction 2-1 j
2.2 Facility Characterization 2-4
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2.3 Flow Calculations 2-5 2.4 CMT level and Mass Balance 2-12
' 5 CMT Local Heat Transfer 2 20 j
2.6 CMT Wall Effects Modeling 2-42 2.7 CMT Wall Condensation 2 48 4
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2.8 CMTInterface Modeling 2-57 j
2.9 Assessment of CMT Rectreulation Tests 2-65
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3.0 Analysis of Core Makeup Tank Test Data 31 I
3.1 Introduction 3-1 l
3.2 Analysis of the 100-Series Tests 3-1
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3.3 Analysis of the 300-Series Tests 3-49 i
3.4 Analysis of the 400 Series Teste 3-97 3.5 Analysis of the 500 Series Tests 3-123 4.0 Phenomenological Modeling Results 4-1 1
4.1 Introduction 4-1 l
4.2 Steam-Region Wall Heat Transfer 4-1 4.3 Pixing Characteristics in 300-Series Tests 4-30 j
4.4 Liquid-Region Wall Heat Transfer 4-37 l
4.5 Comparison of 500 Series Natural Circulation Tests to Calculation Model 4-44 I
4.6 Addressing the Core Makeup Tank Test PIRT 4 50 5.0 Conclusions 5-1 1
6.0 References 6-1
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1 TABLI ^F CONTENTS (Cont.)
Section Title g
APPESVICES A
Calibration Functions Used in Analysis A-1 B
Steam Line Flow Calculations s.1 C
Effects of Flow Measurement Uncertainty on Mass Balance Error C-1 D
CONTRA Sensitivity D-1 E
Integration Cell Size Sensitivity E1 i
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Wall Heat Transfer Modeling i
5 Analysis Elevations Top head elevation:
fluid TC + 2 wall TCs 3 wall elevations:
fluid TC + 5 wall TCs Bottom wall elevation:
fluid TC + 4 wall TCs Inverse Heat Conduction Solution Method per J. V. Beck, B. Blackwell and C. R. St. Clair, Jr.,
" Inverse Heat Conduction - Ill-posed Problems",1985.
Determines local wall heat flux and surface temperature to best fit TC temperature history Calculate local heat transfer coefficient using fluid TC Map Local Wall Heat Flux and Wall Surface Temperature to Axial Profile 100 series tests interpolate results from adjacent analysis elevations 300 series tests l
j time shift results to track changing water level mterpolate results from adjacent analysis elevations l
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CMT TEST ANALYSIS REPORT Conclusion i
Analysis methods developed and used for the CMT test yielded necessary data to:
4 Verify correlations /models for the computer codes Verify the thermal-hydraulic phenomena in the PIRT i
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CMT TEST ANALYSIS REPORT
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i Conclusion Analysis methods developed and used for the CMT test yielded necessary data to:
Verify correlations /models for the computer codes Verify the thermal-hydraulic phenomena irs the PlRT I
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I 100 - SERIES TESTS Steam region heat transfer was correlated using the Nusselt film condenstaion correlation The film Reynolds number was calculated as 4F2 Rer" Et i
i The local heat transfer correlation was calculated as 3
h,a = _4 K Where the average heat transfer is given as P' E' - PJ g k,'
1( = 0.925 plRer The normalized heat transfer is given as nn k, _p,(p,-p )g,
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1 Figure 4.212 Composite Plot of All 100 Series Tests without Noncondensible Gas; Normalized Wall Heat Transfer Coodessation Coefficients i
m:wis2s.-a pt: b.i21*4 4 16
1 i
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i
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r b
i
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Figure 4.2 24 Series 300 Wall Condensation Normalized Heat Transfer Coemcients at
, e psia (685 psis)
. w is m..=..,aiwizi m 4-28
4
_w
.+
GAL..-
u._-mL s
F f
t e
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i s
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[
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8 l
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4
-r
-n
l
!!!itientig CMT TEST ANALYSIS REPORT t
The effects of non-condensibles on the wall condensation were also f
examined i
i Ratio of heat transfer rates from tests with air and without air was i
calculated at various times Three initial air partial pressures were tested Data was compared to the results of Sparrow Data was found to be consistent with Sparrow's analysis 1
l i
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t l
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t I
l l
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Figure 4.217 Comparison of the Wall Heat Flux for Test C047101 (without air) and Test C044106 (ws.h air) at the Lowest Measuring Station E
" W 152s. 4.pfI&120994 4 21 l
l
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4.0 l
r i
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t l
l t
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i Figure 4.218 Comparison of the Wall Heat Flux for Test C047101 (without air) and Test C045107 (with air) at the Lowest Measuring Station m w is2s. a v ik 20994 4-22
- i. -
-. ~.
1 l
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Figure 4.219 Comparison of the Wall Heat Rux for Test C047101 (without air) and Test C046108 (with air) at the Lowest Measuring Station l'
m W t5:s..e.,(.15:20094 4 23 l
t
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l l
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Figure 4.2 20 Comparison of the Calculated Heat Flux Ratio to the Noncondensible Mass Fraction Ratio for the 100 Series Tests and Sparrow's Results mwis2s.4..pt.ib 12:3w 4 24
!amg CMT TEST ANALYSIS REPORT
=
Liquid region heat transfer from the hot liquid layer to the cold CMT walls 1
Data was reduced and analyzed to obtain the local heat transfer coefficients and the Nusselt numbers Different convection regimes were investigated Since the Reynolds number is so low, heat transfer is natural ConVSClion The McAdams correlation, which is used in the NOTRUMP and WCOBRA/ TRAC codes, was compared to the test data
~
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Figure 4.4-4 Comparison of McAdams Convective Heat Transfer Correlation with j
Experimental Data for Heat Transfer from Heated Water Layer to the CMT l
Walls for the 306 Series Tests
{
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t V"']
CMT TEST ANALYSIS REPORT
+..
l Mixing characteristics of the 300 series tests There is an initial high steam flow period in which there is rapid condensation occurring at the steam diffuser i
The condensation induces a steam momentum flux which causes mixing of the subcooled CMT liquid which then enhances the condensation The liquid mixing depth was found to be dependent on the inlet steam momentum i
The mixing and rapid condensation ended suddenly while the bulk of the mixing layer was still subcooled The rapid condensation at the diffuser results in reduced CMT l
draining 1
I l
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T l
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Figure 4.31 Mixing Depth sad Mixed Region Subcooling at End of Mixing Period for 1
l 300 Series Tests l
l m:W1528=-4c.wpf.lb 120964 4-33 l
t m
1 l
l h
l I
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i
(
l 1
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1
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Figure 4.3 2 CMT Axial Huid Temperature Distributions for Test C032310 l
l
=:wis2s.4,t i5: om 4 34
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Figure 4.3-3 CMT Fluid Temperature vs. Time for Test C032310 1
l m:W1528= 4c.wyt.lb 120m 4 35
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muasse Figure 4.3-4 Normalized Final Mixed Region Subcooling and Drain Delay for 300-Series Tests m:W1528=-4c.wyf:lk120994 4.y
II
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emsem i
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Test Data e>- - - - NOTRUMP Figure 4-80 CMT Muid Teamperature for CMT Node 2 for Test 52321 s:u 431.-4.pt.1b.ic:so4 4 91 8
i PREDC.WtY (o M.
l 1
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1 i
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Test Desa e----
NOT1tUMP Maure 4-79 CMT Maid Tesapersenre for Top CMT Nede (Nede 56) for Test 52321 4-90 e:ud31 -4.wyt.tStoassa i
c
-- - ~. -. - -. ~.
PREUMWJty
_fA#)
E r.--
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r-1 Test Data e----
NCmtUMP j
Maure 441 CMT Muid Tempersaare for CMT Node 3 for Test 52321 l
4-92 2
i a:4431=-4.wyf:141028M
?
4 l
"-N'-
1 PRaonwty (4,
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l NOTRUMP Test Data e----
Figure 4 82 CMT Muid Tesaperature for CMT Node 4 for Test 52321 4 93
(
em 431.-4..pt:1b-to2s4
-'T
PRILJMBARY
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F1 pare e Steam Flow late CMT for Test 52321
~
M uA1431w-4.wyt.lb 10294 1
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Hgure 4 84 D sin mw freen CMT for Test 52321 l
I 4-95 t
a:\\1431=-4.wyf:1b102#4 i
(
Punxwiy i
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4 1
% W h at the Top of the CMT for Test 52321 4.,96 sA1431*-5.wyf:1b 102sN
l-gr ng NOTRUMP CMT PRELIK VALIDATION REPORT NOTRUMP METHOD OF CALCULATION FOR AN INITIALLY FULL CMT If no vapor space exists in a node full of subcooled liquid, NOTRUMP will continue to condense steam until the ~ liquid is at or very near the saturation temperature (homogeneous mixing)
Once the liquid is saturated, the vapor can form a region in the cell and all i
subsequent vapor will flow to the vapor space A level can exist in a node with non-equilibrium between the liquid and the vapor phases. The interfacial heat transfer is then calculated by the code Since steam diffuser is submerged in CMT liquid, the homogeneous mixing approach is a reasonable,if not conservative, assumption Homogeneous mixing assumption does make the NOTRUMP CMT model l
noding dependent, judgement must be used Artificial thermal diffusion does exist in the NOTRUMP calculation as the hotter liquid flows between cells and mixes perfectly. This smooths the fluid axial temperature gradient in the CMT relative to the data. This is believed to have a small effect on the overall transient response
( -.- -.
I Pa n M w ty i
. (.e,
1, i.
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4 F1gure 6114 Compadson of the NOTRUMP Calculated Drain Time Delay to the Measured CMT Drais Delay I
j a:\\1431*4 wglb 10:394 4-125 1
i 4
1 PRHlMLMAY 1
w Mgure 4-115 Comparison of NOTRUMP Average Calculated CMT Discharge Mow with Experiments during the Mixing Period before Free Draining Starts 4-126 n:u4n 4=,t.two29e4
~
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l Comparison of NOTRUMP Calculated Mashnom Free W8 M **
Figure 4116 Esperiments ea!431. 6.pr;t> 102
- 4-127
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- -S CMT fr io I I 1
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3............
7 o. co,o.....
l Discharge Line
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Figure 1. CMT Test Facility - NOTRUMP noding scheme CMT Matrix Tests. CMT Draindown at Constant Pressure Test Test no. :ON301 i
e w
CMT: 5 nodes model Elevation If tl Volume lit 31 0
ETOP(56) = 40.1242
~'
l I 6
ETOP(1) = 37.7436 9
VFN(56) = 0.9831 5% tank volumo I
ETOP(2) = 37.2693 1
VFN(1) = 0.9650 5%
2 VFN(2) = 2.8950 15 %
ETOP(3) = 35.8464 3
ETOP(4) = 34.4235 p
VFN(3) = 2.8950 15 %
4 VFN(4) = 11.5800 60 %
EBOT(4) = 28.6833 7
Aug.16.1994
f
{
N ARY 1
i 4
1 (C,N) 1 I
)
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1 I
E 5-Nede NOTRUMP Model; Ceampadsen of the NOTRUMP CN j
F13mre 4117 CMT Drain Delay to the Measured CMT Drain Delay i
4-128 n.uot a.,t.16.tause 1
,,e--
,-w,
l PREUM0WtY l
Ca)d l'
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l Figure 4118 Comparison cf NOTRUMP Coavective Heat Tramfer Coemdent with Expeduwstal Data l
n:u431 4..pt.lb to2994 4 '129 l
l
-n-e..
V'1 NOTRUMP CMT PRELIM. VALIDATION REPORT i
CONCL 3lONS Nusselt laminar film condensation for the CMT walls appears reasonable Most, if not all, small-break LOCA transients will have ample recirculation such that direct condensation effects would be minimized.
4 NOTRUMP homogeneous mixing modelling does not capture the steam momentum effects observed in the test data Current NOTRUMP homogeneous mixing model will over predict a delay in the CMT draining due to condensation if the CMT liquid is cold Use of the McAdams natural convection correlatior ' NOTRUMP will correctly predict the liquid to wall heat transfer The homogenous mixing n.cJet in NOTI (UMP is noding dependent, the SSAR CMT noding appears appropriate. OMT recirculation reduces th;s dependency since condensation is significantly reduced.
NOTRUMP CMT model will be further verified against SPES-2 and OSU data
ll!Fj NOTRUMP CMT PRELIK VALIDATION REPORT i
CONCLUSIONS Phenomena identified in the CMT scaling PIRT have been captured and analyzed Data has been analyzed and compared to the correlations used in the NOTRUMP code Tests have identified areas where modelling improvement will be used, use of Nusselt film correlation Tests have confirmed that the application of the current SSAR CMT noding is conservative
..he h h eh h.4 42h mLhm4h Ah & ~4. A b.hu4.'_ h e ss,.me.644ph WA ^
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- ' MM4 E M he+6he MM -- -
Amebe.hhmYhe %4h ukA44Nh.h e.O &.a. h-ML.sh ES Lh AEuheh 4.Gn.bmMM, NOTRUMP CODE APPLICABILITY DOCUMENT w
f i
BOB KEMPER NUCLEAR SAFETY ANALYSIS l
1 s
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^
NOTRUMP CODE APPLICABILITY DOCUMENT
~
NOTRUMP Evaluation Model Developed to address Post-TMl concerns regarding SBLOCA l
NUREG-0611 NUREG-0623 NUREG-0737 Provides better estimate thermal hydraulics Provides spatial representation of system Contains special component models Core model Steam generator model RCP model Verified against separate effects and integral test facility data i
i
pr,g NOTRUMP CODE APPLICABILITY DOCUMENT J
i NOTRUMP Capabilities l
Flexible nodes, flowlinks, heatlinks approach l
l Generalized non-equilibrium in all nodes Flow regime maps utilized l
Vertical upward / downward Horizontal Used for drift flux and heat transfer correlation selection Vertical node stacking capability Stratified fluid nodes Eliminated steam / liquid layers (i.e. pancaking)
Axial void distribution calculated Flow path drift flux models consistent with node bubble rise models Horizontal stratified flow paths Co-current and counter-current Flow regime dependent stratification
TABLE OF CONTENTS Title
.P,_gge Section I
SLM1ARY 11 1.0 Introduction 12 1.1 Historical Background 13 1.2 NOTRUMP Modeling Capabilities 15 1.3 Application of NOTRUMP to Small-Break LOCA ECCS Analyses 17 1.4 Important Small Break LOCA Transient Phenomena 2-1 l
2.0 Range of Applications of NOTRUMP Small-Break LOCA Analyses 21 l
2.1 Comparison of Key Plant Parameters 2-2 2.2 AP600 Design Differences Affecting Small Oreak LOCA Analyses 3-1 l
3.0 NOTRUMP Modeling of AP600 3-1 l
3.1 Introduction 3.2 NOTRUMP Code Possible Enhancements for AP600 32 3.3 NOTRUMP Code Externals for AP600 3-2 41 4.0 Validation of the NOTRUMP AP600 Modeling 4-3 4.1 Test Simulations 4-4 4.2 Compliance with Appendix K 5-1 5.0 Conclusions 6-1 6.0 References l
l l
i l
l a:\\1t$1w.wpf:1b 111794
[jj
pru!ll NOTRUMP CODE APPLICABILITY DOCUMENT "L.I AP600 Primary System Design Differences Do Not Affect NOTRUMP Applicability Used in SBLOCA calculations for the CE 2HL*4CL layout Canned motor pumps simplifies the RCS layout (no loop seals) 4
_. = -
TABLE 21 COMPARISON OF KEY PLANT PARAMETERS Typical 2 Loop Addrussed in '
Key Plant Parameters AP600 PWR NOTRUMP via Steam Generator Delta-75 51 Input Reactor Coolant Pump Canned-Motor 93A AP600 has no loop seals:
RCP region renoded MSSV Setpost (psia) 1100 1100 Input Number of Fuel Assemblies 145 121 Input 264 179 Input l
Fuel Rods / Assembly Core Power Level (MWth) 1933 1615 loput FQT 2.60 2.40 Power shape input F-delta-H 1.65 1.75 Power shape input Accumulasor Pressure (psia) 700 700 Input l
Safety Injecuon Passive Systems HHSI, LHSI Nodal ww*le of AP600 PXS are derived l
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yr,y NOTRUMP CODE APPLICABILITY DOCUMENT Passive Safety System Performance of NOTRUMP Requires Validation i
l CMT, ADS Phase B simulations l
SPES-2 and OSU integral test facility simulations i
l
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NOTRUMP CODE APPLICABILITY DOCUMENT l
1 AP600 NOTRUMP Methodology An evaluation model analysis Appendix K decay heat Critical flow models:
Zaloudek/ Moody for break (s)
Henry-Fauske/ HEM for all ADS flow paths Only safety-related systems modeled Worst single failure assumed l
Spectrum of breaks from inadvertent ADS actuation to the double ended direct vessel injection (DEDVI) case executed to confirm ADS and passive safety injection system capability i
i- -.
y NOTRUMP CODE APPLICABILITY DOCUMENT improvements Being Made to NOTRUMP for AP600 Note: These modifications are all in the process of being developed and tested Eliminate discontinuities associated with flowlink transition from co-current to countercurrent flow Improve flowlink model ability to cope with rapid density changes for low pressure stability Improve capability to model the introduction of highly subcooled water into 1
an all-vapor node Improve the horizontal-stratified flow link model Improve the code's ability to pass a mixture level from one node to another Treat bubble rise within a stratified fluid node implicitly Condensation modeling (Nusselt correlation, etc.)
Logic for the AP600 passive safety system actuation and performance
i iipr nig NOTRUMP CODE APPLICABILITY DOCUMENT Tl
\\
==
Conclusions:==
f A NOTRUMP Evaluation Model for AP600 is being created Appendix K conservatism remains in the SSAR plant calculations Code applicability is validated via the test simulations l
Design modifications have increased the LOCA margin in the plant Current NOTRUMP analysis indicates no core uncovery up to DEDVI line break sizes The net result is an SSAR analysis which utilizes better estimate l
thermal-hydraulics within the Appendix K framework i
l i
pr, t
CLIT TEST ANALYSIS REPORT u.
l l
1 t
4 Natural Circulation Behavior i
i Rick Wright I
I
.i i
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l
)
e
gr,ig CMT TEST ANALYSIS REPORT
_ n.
Natural Circulation Tests - 500 Series 1
Nine tests were performed to study natural circulation in the CMT Tests were performed at 1085 psig and 1835 psig, and continued until the CMT was heated to various levels 20% heated l
50% heated 4
t Fully heated In the second part of the tests the CMT was drained, coupled with depressurization of the system An analytical model was developed and presented in the CMT scaling report to provide pretest predictions and to evaluate the results of the natural circulation tests These results are also presented in the CMT Test Analysis Report, Sections 2.9 and 4.5 i
i b
CMT TEST ANALYSIS REPORT Natural Circulation Analytical Model Model consists of an energy balance which matches:
a thermal driving head due to the elevation change between the cold CMT and the hot S/WR 1
non-recoverable losses around the recirculation path
( [ K,,,, + ") h}
O L ( pc - pn) = 2g,[ ( [ K,,,, + D)c A
+
D nA 9c n
c t
l i
This model is applied using the initial conditions of the test to i
determine the natural circulation flow l
l l
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Test Comparison to Natural Circ. Model Test No. C064506
/
_7 g
5, 6
g h
I
/
l A.
I
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! /'
X 1
l
- 0. -
0 100 200 300 400 500 600 700 Tune (sec)
Test a Model i
l l
Figure 4.51 Hot Liquid Layer Thickness Comparison, Test C064506 mpiS21. 4e wpf.Ib.121594 4-46 I
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5 l
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1 l
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l l
l
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Figure 4.5 2 CMT Discharge Flow Comparison, Test C064506 I
mWis2s. 4e.wpt:ib-121394 4 47
l l
CL M l
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i Figure 4.5 3 Hot Liquid Layer Thickness Comparison, Test C072509 l
(
mw15:s.-4e wpf:15:21394 4-48 l
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l
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Figure 4.5-4 CMT Discharge Flow Comparison, Test C072509 i
f m:W152s. 4e.-pt:15 2 394 4 49 r
i L
e CMT TEST ANALYSIS REPORT l
CONCLUSIONS 1
CMT recirculation behavior is accurately predicted using the model i
from the scaling report i
During the drain-down phase, flashing due to system depressurization did not have a significant effect on CMT drain rate i
i l
l l
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_.e.E "bp.h.WA-Ah hen +E4 M.h w h 4 6msR._ S phh hh--
e4 Al8%N Wh=be4&aM4 hh_m 4Ne a4 hhD
--' ' % & B.m
- - ^
.4 M _ E4 4 R h 4 & e..m.ES, W ham 4 444.nhB.h enmOb 4.
M b &.642_mh hE A5 h da sa l1lprugj NOTRUMP CMT PRELIK VALIDATION REPORT L?
r L.E. HOCHREITER NUCLEAR SAFETY ANALYSIS f
t 1
a a
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!!!Pf~']
NOTRUMP CMT PRELIM. VALIDATION REPORT
+
INTRODUCTION NOTRUMP was used to model the 300-series CMT tests Models that were examined were:
Wall condensation Steam condensation / mixing Thermal stratification / diffusion Convective heat transfer to cmt walls Other aspects of the calculation that were examined were:
Test facility flows, steam and drain CMT pressure behavior Fluid temperature distributions
,... -. - - -... - - - -... - _. - - -. -. -. - - - _ _ -.. - -. - - -. ~. _ _ -.. -
NOTRUMP CMT PRELIM. VALIDATION REPORT l
CMT 100-SERIES TESTS l
l Tests provided data on wall condensation Nusselt laminar film condensation bounded the majority of the data over the range of conditions Nusselt correlation will be used in NOTRUMP 4
1 1
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I Figure 61 Series 100 Wall Condensadom Nonneliand Heat Transfer Coeffidents at 25 to 1100 psia (10 to 1085 pois)
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I
' ~ ~ -
a
png NOTRUMP GMT PRELIM. VALIDATION REPORT O
CMT 300-SERIES TESTS Tests were initiated with cold CMT liquid and walls Recirculation phase was not modelled such that condensation was maximized in these experiments to test the code Steam diffuser was used which limits the condensation effects Tests were performed over a range of pressures and drain flows The drain flow rate is a dependent parameter in the experiments and is determined by the CMT system response Tests would simulate the result of a large-small break LOCA or a large break LOCA i
SIealii supply pressure!
CMT O
ko
"=' 5 """>
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0 Steam Line no.1 U
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.h 4. Fluut Nod.
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+ i-i.e ac-a...u.on j
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Figure 1. CMT Test Facility - NOTRUMP noding scheme CMT Matrix Tests. CMT Draindown at Constant Pressure Test Iest no. c302
R ETOP(56) =_40.1242 I f 7
MN56 56 10 %
/
(top T node)
/j ET0P(2) = 37.2693,,
V
/
2 is %
/
MN2 ETOP(3) = 35.8464 A
/j
//
3 15 %
/
fliN3 ETOP(4) = 34.4235 A
7,//-
3 j
/
l f
/
4 60 %
MN4 EBOT(4) = 28.6833 u
- Flow Link ETOP - top elevation of Fluid Node
- Fluid Node EBOT - bottom elevation of Fluid Node 4
- Metal Node 10 % - part of CMT total volume Jun.27,1994
.s o
.n,
P1tJ1DedtY
_4, i
1 l
i Maure 4 9 CMT Muid Temperature for Top CMT Node (Nede 56) for Test 37301 aM431w-1.wytth1028M 4-20
i PRELD@RRY I
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Rgure 410 CMT Muid Temperature for CMT Node 2 for Test 37301 i
es431....gib.102p4 4-21
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l PRf1DtIMRY Coh l
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Figure 411 CMT F1mid Teamperature for CMT Nede 3 for Test 37381 1
i MU eA1431,1.wyttblessD4 6
4,
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1 Figure 4-12 CMT Fluid Temperature for CMT Node 4 for Test 37301 i
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I Meere 413 Steous Mew late CMT fler Test 37301 l
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L Figure 414 Drain mw froni CMT for Test 37301
- - ~ -
~
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s 4
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e gemi Figure 615 Pressere at the Top at the CMT for Test 37301 a:us31.-l..pt.151 oases 4 26
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