ML20199C499
| ML20199C499 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 11/11/1997 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19313D085 | List: |
| References | |
| ACRS-GENRAL, AW-97-1184, NUDOCS 9711200037 | |
| Download: ML20199C499 (207) | |
Text
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- etil C0 Of81100- AW-97 1184 -
November 11,1997 DNument Control Desk
- U.S. Nuclear Regulatory Commission Washington, DC 20555
- ATTENTION: MR; T. R. QUAY APPLICATION FOR WITilllOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE SUl3 JECT: ACRS TIIERMAL-ilYDRAULIC PilENOMENA SUBCOMM11 TEE MEETING -
WESTINGilOUSE AP600 PASSIVE CONTAINMENT COOLING SYSTEM TAP, ROCKVILLE, MD, SEPTEM'3ER 29-30,1997
Dear Mr. Quay:
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.
Se proprietary material for which withholdmg is being requested is identified in the proprietary version of the subject report in conformance with 10CFR Section 2.790, Affidavit AW-97-Il84 accompanies this applicmion for withholding setting forth the basis on which the identified proprietary informat i on 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 aspect to this application for withholding or the accompanying affidavit should reference AW 97-Il84 and should be addressed to the undersigned.
Very truly yours,
- [//'
Brian A.- McIntyre, Manager
' Advanced Plant Safety and Licensing
^
jml cc: - Kevin Bohrer NRC OWFN MS 12E20 i
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AW-97-1184- '
- " g AFFIDAVIT.
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i COMMONWEALTil OF PENNSYLVANI A-SS COUNTY OF ALLEGilENY:
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 ou behalf -
of Westinghouse Electric Corporation (" Westinghouse") and that the avennents of fact set forth in this -
Affidavit are true and correct to the best of his knowledge, information, and belief:
A /8 #./ ,M '
Brian A. McIntyre, Manager Advanced Plant Safety and Licensing Sworn to and subscribed -
before me this MM day of /fATMonft/AJ ,1997 sid / /Att
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I AW-97.ll84 (1)' I am Manager, Advanced Plant Safety And 1.icensing, in the New Plant Projects Division, 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 em authorized to apply for its withholding on behalf of the Westinghonse Energy Systems Bus....ss Unit.
(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 l withholding accompenying this Affidavit. 1
-(3) I have personal knowledge of the criteria end procedures utilizec Ly the Westinghouse Energy Systems Business Unit in designating information as a trade secret, privileged or as confidential commercial or financial information.
1 1
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's
- regu!ations, the following is furnished for consids ration by the Commission in determining whether the information sought to be withheld from public disclosure s.hould be withheld.
(i) The information sought to be withheld from public disclssure 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 t( determine when and whether to hold cecain 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.
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:
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AW 97.I184 l l
(a) - The informatian reveals the distinguishing a3pects 'of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advaatage over other companies.
(b)_ lt consists of supporting data, including test data, relative to a process (or component, structure, too!, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use by a competitor would reduce his expenditure of resources or improse his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product,-
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers. .
(c) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(0 It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse givo Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Wertinghouse competitive position.
(b) It is information.which is marketable in many ways. The extent to which such information is available to competitors diminishes the Wes;inghouse ability to sell products and services involving the use of the information.
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~ AW 971184 -
P (c) . Use by our competitor would put Westinghouse at a competitive disadvantage
- by reducing his expenditure of resources at our expense.
(d)- Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage, if competitors acquire components of proprietary information, any-one component may be the key to the entire purzle, thereby depriving Westinghouse of a competitive advantage.
(c) Unrestricted disclosure would jeopardize the position of prorninence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f) The Westinghouse capacity to invest corporate assets in research rid development depends upon the success in obtaining and maintaining a competitive advantage.
(iii) The information is being transmitted to the Commission in confidence and, uader the provisions of 10CFR Section 2.790, it is to be received in confidence by the - y Comm:ssion.
(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.
(v) Enclosed is Letter DCP/NRCl123 (NSD-NRC-97-5424), November 11,1997, being transmitted by Westinghouse Electric Corporation (%) letter and Application for Withholding Proprietary information from Public Disclosure, Brian A. McIntyre (W),
to Mr. T. R. Quay, Office of NRR. Tbc proprietary information as submitted for use by Westinghouse Electric Corporation is in response to' questions concerning the
' AP600 plant and the associated design certificction application and is expected to be applicable in othei licem ibmittals in response to certain NRC requirements for
AW.97-1184
. . justification of licensing advanced nuclear power plant d: signs.
This information is part of that which will enable Westinghouse to:
(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.
(d) Establish technical and licensing approaches for the AP600 that will ultimately result in a certified design.
1 (c) Assist customers in obtaining NRC approval for future plants.
Further this information has substantial commercial value as follows'.
(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.
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 services for commercist power reactors without commensurate expenses. Also, public 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 information.
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. . . . - - . . . . . . _ . ~ . ... . . - . . . .. .. - . . . - . - . . - . . . . - - . .
AW 971184 L
'.t-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 Wes' tinghouse effort - -i g .
and the expenditure of a considerable sum of money, ,
In order for competitors of Westinghouse.to duplicate this information, similar : (
technical programs would have to be performed and a significant manpower effort, e
- having the requi.ite talent atid 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- WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-l g ACRS THERMAL-HYDRAULIC PHENOMENA SUBCOMMITTEE MEETING l
WESTINGHOUSE AP600 1 PASSIVE CONTAINMENT SYSTEM TAP
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t Rockvil!e, MD September 29-30,1997 ]
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- ~q Meeting Objective ,
l Demonstrate the experimental database for the AP600 containment Evaluation Modelis sufficient to support validation of correlations implemented in the analysis code and in the i
AP600 Containment Evaluation Model inputs.
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ACRS 9/97 2
3 Day 1 Agenda i
Introduction Meeting Objective Status / Use of PCS Documentation Plant Description Test and Analysis Process Roadm6p PlRT Purpose c~ DIRT Accident Specification l Process for Phenomena identification & Ranking l High & Medium Ranked Phenomena i
l Scalina 1
AP600 Phenomena Assessment l Range of Parameters l System Level Scaling l
AcRS 9/97 3
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.i l Day 2 Agenda -
l L
l Introduction 4
i
- DBA Pressure Evaluation Model Approach Evaluation Model Requirements Features Handled within WGOTHIC Code i Features Handled outside of WGOTHIC Code t Validation Process 4 t
e Circulation / Stratification Database L
Industry Experience Known Limitations How Limitations are Addressed 'l
- Validation of AP600 Correlations ACRS 9/97 4
--..---------i. . .
l L .
Topics for December Meeting .
AP600 Containment Pressure DBA Evaluation Model l Description of WGOTHIC Code Lumped Parameter Formulation Equations ,
Numerics WGOTHIC Lumped Parameter Comparisons to LST WGOTHIC AP600 Lumped Parameter Model Approach Validation of Correlations Outside WGOTHIC -
Circulation and Stratification :
Water Coverage / Stability Conservative Model for Calculation Peak Pressure ACRS 9/97 5
l l
t PCS Licensing Documents
- PIRT WCAP-14812, Rev 1, June 1997 i'
Scaling WCAP-14845, Rev 2, June 1997 Heat & Mass Transfer WCAP-14326, Rev 1, May 1997' WGOTHIC Validation WCAP-14382, Rev 0, July 1995 WGOTHIC Upgrade Assessment WCAP-14967, Rev 0, Sept.1997-WGOTHIC Application WCAP-14407, Rev 1, July 1997 AP600 SS AR t AGRS 9/97 6
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PCS water supply and timing '
- Sequence of Events as PCS Cooling Film Develops Time Event. (sec.)
Break triggers containment 0 pressure setpoint Valve opens 20 '
1 (Jipe and bucket fillsolenoid-actuated, 37 air-operated)
- First weir fills 112
- Second weir fills 187
- Steady coverage established 337
! ACRS 9M 9 i
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aun um em uma uma um aus sus uma sus um aus sus sum aus an uns aus um Comparison of AP600 to Standard Westinghouse 2-Loop Plant -
i i Plant Feature AP600 Standard 2-Loop Plant
- NSSS Thermal Power 1940 MWt 1880 MWt (Power / Volume) (1.14 kw/ft') (1.45 kw/ft )
Containment Diameter 130 ft. 109 ft.
Net Free Volume 1.7 x 108 ft' 1.3 x 108 ft Approximate Exposed Mass Available for Heat Sinks Concrete 14.7 x 10' Ibm 14.3 x 10s gg Steel 7.8 x 10' lbm 1.9 x 10' lbm Long-Term Heat Removal Passive Cooling Active systems ACRS 9M 11
7
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l DBA Containment Pressure Regulation -
Reactor containment shall establish an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment and to assure tt.at the containment design conditions important to safety are
! not exceeded for as long as postulated accident conditions require. (Criterion 16). .
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ACRS 9/97 12 l
mM M M M M M M M emM M emee em!
i INE DBA Containment Pressure Regulation j -
The system safety function shall be to reduce rapidly, consistent with the functioning of other associated '
l l systems, the containment pressure and temperature
! following any loss-of-coolant accident and maintain '
l them at acceptably low levels for onsite and offsite l .
electric power system operation assuming a single i
failure. (Criterion 38) 4 Acas s,w 13
DBA Containment Pressure Regulation ,
~
The containment structure should be able to
- accomrnodate the calculated pressure and j temperature conditions resulting from any LOCA. I
- This is to be accomplished without exceeding a l design leakage rate and with sufficient margin. The
! margin should reflect consideration of (1) potential
! energy sources... (2) limitations on the amount of information available on accident phenomena, and ,
(3) conservatism in the calculations (Criterion 50).
I4 ACRS 9M
1 Accident specification i
Containment Pressure Criteria
! P poog <= P syn (45 psig) New methods for AP600
{ P,in >= (-3) psig SRP methods
. AP eompanment <= 5 psi SRP methods SRP methods
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AGRS 9/97 15
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Criteria spe~cifically supported by the PIRT
! - Documentation in an application for design certification should include:
L evidence that the performance of each safety feature of the design
! has been demonstrated through either analysis, appropriate test programs, experience, or a combination thereof
! (10CFR52.47(b)(2)(i)(A)(1) )
i evidence that sufficient data exist on the safety features of the design to assess the analytical tools used for safety analyses over a ,
l sufficient range of normal operating conditions, transient conditions, and specified accident sequences (10CFR52.47(b)(2)(i)(A)(1) )
1 ACRS 9/97 16
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Test and Analysis Process ,
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- . Evaluate Distortions Validate Models and Correlations PIRT; #
for Scaled SET -+ Condensation (LST, Wisc) -->
l idemify and Rank Evaporation (G&S, Flat Plate)
Phenomena WCAP-14845, Rev 2 Above-deck Stratification (LST, Others)
Sed III Water Coverage (LST, WDT, WFPT, SST)
WCAP-14812, Rev 1 PCS Air Flow Resistance (1/6 Scale) ;
i Circulation (International Database)
,. Evaluate Distortions 4
for Scaled IET Confirmation of Lumped Parameter .
Phenomena Scaling, "-* -+ Biases and Capabilities ,
Validate PIRT WCAP-14845, Rev 2, Dimensionless Gioups Sect til WCAP-14407, Rev 1 Sect. 9.1.2 & 9.2.3 AP600 Range Develop Conservative S eg es / Wels f
WCAP-14845, Rev 2 Sect 11 ,,,,,
WCAP-14812 Rev 1. Sect. 4.4 Select Computer identify Code Biases Apply Biases to Code Models and inputs Predict Plant and Capabilities >
Performance
- WCAP-14407, Rev 1,
- WCAP-14382 - WCAP-14407, Rev 1, Sect.3, Sect. 9.2.4 WCAP-14407,79 v 1 Sect. 3 SSAR 6.2 .
Sect.3 and Sect 9.C.3 and Sect. 9.C.3 WCAP-14967 ACRS 9,97 l7
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- September 29,1997 l Presented by:
! Joel VVoodcock i
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! Accident Specification & PIRT .
Outline
- Purpose of PIRT and its process j Process for phenomena identification and ranking l
Accident specification ,
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- Summary of High and Medium ranked phenomena l 1
i PIRT process summary i.
ACRS 9/97 2 i
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- i Purpose of PIRT and its process
- The Phenomena identification and Ranking Table (PIRT) and the related process:
Identifies important transport processes and phenomena Ranks phenomena to focus attention on the most significant influences on containment pressure Identifies asaects of the AP600 containment to be addressed in the bounding Evaluation Model 4
ACRS 9/97
! 7 31:
Purpose of phenomena ranking i
The phenomena ranking:
Establishes the most important processes for i
l mitigating containment pressure rise; and j Provides guidance on the appropriate leve; of detail in assessing phenomena or developing bounding models i __ _ . _ _ _ - - _ _ _ _ _ ____--_ -- . _ .. .
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Process for phenomena identification and ranking
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aa PIRT documentation 1
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Current documentation (WCAP-14812, Rev.1) of l ranking basis includes PIRT process description l Plant design description, accident specification, and criteria l
! Testing program synopses Ranking bases (Testing, Scaling, Sensitivities, Expert review) ,
t How phenomenon is implemented in Evaluation Model (EM) j Justification of EM treatment of phenomenon (Test l experience, Modeling guidance, Sensitivity studies)
EM treatment of uncertainty, distortions ACRS 9/97 7
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- Specify plant design information ,
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a Specify accidents and partition temporally L
Select target parameter and ranking bases .
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Organize phenomena spatially L -
Rank importance of phenomena Determine evaluation model approach for important phenomena l
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' ACRS9/97 8
PIRT ranking basis Transport processes and phenomena are ranked on the basis of:
Their effects on pressure (internal to containment)
- Their effects on energy removal mechanisms or momentum (external to containment) j -
Expert ranking is based on experience and judgement Rank.ing considers expert opinion combined with Test results Magnitude of terms in AP600 phenomena assessment Results of sensitivity studies 1
ACRS 9/97 9
How phenomena are treated in S f
containment DBA evaluation model
- High or Medium ranking during any time phase Phenomena with a High or Medium ranking during any LOCA time phase or during an MSLB need to be considered in the evaluation model. Consideration may include showing that neglecting a phenomenon is conservative for pressure predictions.
Low ranking during all time phases
- Phenomena with a Low ranking during allLOCA time phases and during a MSLB i are those that have a small effect on pressure. As a result, it is acceptable to use an available best-estimate or realistic model in the evaluation model. In some cases, the low ranked phenomenon may be neglected if its effect on containment pressure is small or if it would be conservative with respect to l containment pressure to neglect it.
i ACRS 9/97 10
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- with containment structures .
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Phenomena are listed from inside, through the
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l Each energy transfer process has been l assigned to the component or volume to which 1
the process is most closely associated, and with the energy source Parameters important for containment cooling process, such as Initial and Boundary Conditions, are included 13 ACRS 9/97 4
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PIRT focuses code validation and i
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- leads to evaluation model definition PIRT Evaluation Model - Code Validation m l Key Elements t
- y Bounding Models No ,
Phenomena reports identified?
Test reports Yes Sensitivity calculations V 1
Expert review WCAP-14812, Rev.1 Sect. 4.4 documents for Scaling report H, M, L phenomena:
- Ranking bases
- How phenomenon is implemented in EM
- Justification of EM treatment of phenomenon
- EM treatment of uncertainty, distortions ACRS 9/97 15 ,
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Accident Specification & PIRT -
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Accident specification
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LOCA DECLG sequence and temporal partitioning .
Relative heat sink heat removal rates MSLB response characteristics l
ACRS 9/97 17
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LOCA DECLG Sequence of Events ,
i Time l
(sec.) Event O Break occurs, blowdown begins, actuation signal generated 20 PCS valve opens 30 Blowdown ends, refill begins 37 Water begins to spill onto dome 90 Refill ends, peak pressure phase begins 337 Steady state shell water coverage assumed to begin (440 gpm) 1,200 Peak pressure phase ends, Long-term depressurization begins 12,937 PCS water decreases to 122 gpm 36,000 IRWST subcooled water inventory depleted 110,137 PCS-water decreases to 72 gpm 259,537 PCS water decreases to 63 gpm ACRS 9,97 18
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< l 1 1 I 10 100 1000 1E04 1E05 t
Time (sec)
ACRS 9/97 19
_. __ _ ______ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ - _ ~ m . . _ . .
Intemal containment diagram is i ,
- simplified based on sink locations Le W of the Sreeks Y to apetee Jets A33 Stage 4
- - ^p I?S" mn af n .m meme e.a.
g# j
X Yanni.'"
135- / 135* 135*
C'77/Z7/7/) / $G 7H/wsww- pw/aW HsWHA &
- CMT CMT ; w I
(
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-- _$m .r__ v ser -
-- r
- g - 'ar l Ti ~.
5 '"
., i;
- . '* W ,/ :- : ;
,. =carta= cav"' 7
" 2 01 f~~
-. . t
,. // ,
- f. : '. . .
. . . 1.,....
20
' ACRS 9/97 . . r .. . . .
~ '
s.
_: ' , . '"~ T ' * . . '. ~-' *: .'.' * , " '. J '. * - l .l '.: *._ ".'..
um um um Oma en am um as == == == a= == = m. e O.
L LOCA: Maximurn internal heat sink effectiveness is l 'E reached as PCS cooling becomes effective 50
- 275,000 _
- 9
-*;;%4 45 m 250,000 A i
.3 225,000 _ - -
4 -
40 3 : .
g x 175,000
_ l
! 4.
\I -
35 30.g A 150,000 ~_ ; g, 125,000 ~l
- 6
['. \ ---
25 2
~
- /
[~ ~ e's _
m 20 I g '" ** ii l / a.
5 Y .., , 'e, N., 15 l
25,000 V
- - /..... N A : L
- - - . ~,
~~' w i io
~-
- t:.eg m ,, ,___ __, *-* T ~~i 5 0 7-
. . ....i
. . ,..... . . . . . . . . O
) (25,000) 100,900 10 100 1,000 10,000 1
Time (ac)
SG West M.CMT RCIFT C W S.CMT Abew. Dort Q_he qg Dead Beded Cesaportenemes SG East PCs M Cu veemums 4 Velmsmo tu Veheme ite valesman t>et Vetenes3.2.3,0,A 193 Vehemes 4 & 197 Valemmes5 4 908
. . . . . . . . . . . . . . . . . . . ---- -e- -
- ....... ...Q...
m
. y;a ;, , ;, ;; y y, ;;
' ~ '
PCS water supply and timing relative to EM external temperature -
Sequence of Events as PCS Cooling Film Develops Time External Dome Activity (sec.) Surface T(F) (1)
Break triggers containment 0 120(2) pressure setpoint Valve oaens 20 120 '
(solenoid-actuated, air-operated)
Pipe and bucket fill 37 121 First weir fills 112 134 Second weir fills 187 144 l Steady coverage established 337(3) 174 l
(') Tcalculated using containment EM with no credit for water on shell until337 s.
(2) Initial temperature is assumed at Tech Soec maximum for PCCWST .
(3) Conservative bound of Water Distributioh Test data 22 ACRS 9/97 l
_ ; _ g_gg_g_ggg__g MSLB Typical Containment .:
Pressure Response MSLB releases are over by ~400-600 seconds, and PCS water application delay assumed in EM results in internal heat sinks remaining dominantduring release period.
I 4
l a
. m l
. tn l w >
i l x
- a. l i
l I i O 1000 2000 3000 4000 i.
TIME (sec)
ACRS 9/97 23 i I
Summary of key AP600 containment ;
^
~:
- pressure response characteristics Two limiting accident scenarios have aeen identified LOCA (four time phases) and MSLB (single time phase)
A review of heat removal rates shows that LOCA: Internal heat sinks are dominant early and reach maximum thermal effectiveness before second peak
- LOCa; Dominance transitions from internal sinks to PCS as l
pressure is turned around LOCA: PCS is dominant at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> MSLB: Internal heat sinks are dominant ACRS 9/97 24 i
Accident Specification & PIRT .
Summary of High and Medium ranked plenomena 25 ACRS 9/97
=
Summary of High and Medium ranked
~
5 phenomena A process has been documented that identified 81 total phenomena,
- transport processes, and parameters for containment pressure ranking bases, including expert review, are documented 37 phenomena are H or M during at least one phase H, M, and many L phenomena are treated and bounded in evaluation model A high level grouping provides a focus for model development t
- Break source - Gas compliance - Initial conditions
- Condensation - Internal solids / pools - Evaporation
- Convection - Radiant heat transfer - Film energy transport l
- Baffle conduction / leakage Parameteric relationships with other phenomena can then be identified ACRS 9/97 26
l l ::
Accident Specification & PIRT -
PIRT process summary ACRS 9/97 27'
I na~
PIRT process; summary 1
The process used to identify and rank phenomena for the AP600 containment DBA was based on results from
- scaling arealyses - test programs
- expert review - sensitivity studies
- theory and ranging external to WGOTHIC The process allowed the identification of the most important phenomena for reducing the containment pressure and transferring .
energy to the environment I
The containment DBA PIRT is used to identify phenomena which need to be addressed in the containment Evaluation Model -
structure the development of a conservative evaluation model ACRS 9/97 28
=.-------.-r-----.,-,. - , , ,-- -- y ,ng.-g .a ,pa , ,4_.w4a ns , ,_,am.m4a..a .,m,mm.,.4a, a .c ,_ e mp .g,,m _.%,,p., ,,pg m.aen..e..am-.- ._.e.m w .- m -4m. maw I ,
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.i f
i AP6C0 Phenomena Assessment l
i Presented to the ACRS i
9/29/97
^
by D. R. Spencer ACRS 9/97 1 i
AP600 Phenomena Assessment ; :_.
Topics -
i AP600 Phenomena Assessment Model j
- j. Components l
l Transport Processes ;
! . Radiation, Convection Heat Transfer, Convection Mass Transfer '
Rate of Change Equations Mass, Energy, Pressure, Momentum >
Model Prediction Comparisons ;
Pi Values Dimensionless Parameters Range Phenomena Assessment Model Comparisons ACRS 9/97 2 ,
i'
AP600 Phenomena Assessment i i
l l
l l
l Phenomena Assessment Model (WCAP-14845, Rev 2, Sect. 4, 6, 7) i ACRS 9/97 3
. . . . . . . . . . . . . . _u 4
4
~
Phenomena Assessment Model E i
Mass and energy transport processes couple the component / volumes. The i containment atmosphere is coupled to the liquid heat sinks, solid heat sinks, and shell.
The shell is coupled to the PCS air flow path and baffle. And the PCS air flow path is coupled to the baffle, shield building and chimney. !
Heat Sinks: Transport Processes '
- Gas: Containment, PCS Air Flow Path -
Radiation Heat Transfer (Downcomer, Riser, Chimney) -
Convection Heat Transfer !
Liquid: Drops, films, break pool, IRWST -
Cond/Evap IWass Transfer Solids: Shell (Dry, Subcooled, Evaporating) !
1-D Conduction HeatTransfer and solid heat sinks (steel, concrete, Enthalpy Transport jacketed concrete) l ACRS 9/97 4 f
a d
Energy F ow Diagram ~ ~
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sa wm+ 1 u s$ n =w ,: ;
. e ma, -
S e m . ..a e u a;&anty. Pyr w M u %,
- g fr r . .
r = radiation gggg~ i B,re,t ac -
c = convection
='
i m = mass transfer ,
i ACRS 9/97 5 f
i
i Heat Sink Energy Equations .
=
Gas volumes are modeled as lumped parameter volumes, while the liquid and solid components are -
modeled by energy equations selected to model the unique characteristics of each. The energy interactions between the gas volumes and components are modeled using integral equations and otheriechniques to simplify the otherwise complicated time integration for each heat sink.
?
Heat Sink Modeling Method Modeling Basis Drops, d Equilibrium Drop time const << 1 sec Break Pool, p Equilibrium (blowdown), Maximize evap, i Evap from a surface layer Rate limited Internal Film, if Steady-state conduction, no cv (mcvDT) film << (mc vDT) heat sink Internal Steel, st Lumped parameter Bi < 0.13 Internal Concrete, cc integral equation Semi-infinite conductor -
Jacketed Concrete, jc The larger flux for (steel, concrete)Short term steel, long term concrete Shell, sh Integral equation Thermally thick, two sided plate Baffle, bf Lumped parameter Bi < 0.0044 Chimney Concrete, ch Integral equation Semi-infinite conductor ACRS 9/97 6
, a ; _;_ ;; ; _ ;;;;;_ a ; ;;
Radiation Heat Transfer -
i i
i Radiation heat transfer can be written in terms of a conductance and a !
temperature difference- i q/' = as(T4 -T,4y) !
or q/' = h,(T -T,y) !
l 2 2 where the conductance is h, = oef(T,T,y) and f(T,T,y) = (T + T,y)(T + T ,y). The
! character e is the surface eraissivity for surface-to-surface radiation, and the product of the emissivity and beam length for radiation from the containment gas to the surface.
I ACRS 9/97 7
Convection Heat Transfer -
Laminar / Turbulent and Free / Mixed / Forced Convection inside Containment Lam /Turb: Turbulent free convection heat transfer is expected for Grashof number (based on height) > 109 1 This is the case over all but 2 feet or less of height of heat sinks and the shell t The turbulent free convection correlation underestimates heat and mass transfer at Grashot numbers less than 109, so its use is conservative for smaller structures or early time values.
, Free / Mix / Force: Insufficient data are available to support forced or mixed convection models for the inside of containment, so the inside of containment is modeled using turbulent free convection throughout the LOCA and MSLB transients.
Outside Containment The PCS air flow regime is determined from the Eckert and Metais plot.
Lam /Turb: Turbulent Free / Mix / Force: Forced in riser and downcomer, free / mixed / forced in chimney ACRS 9/97 O
i ; i;jij t l ( r ;i.[' I ' ;> , l
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Convection Heat Transfer : ;
Correlations -
1 Turbulent Free Convection Heat Transfer i The McAdams correlation was selected for scaling turbulent free convection :
4 heat transfer for all surfaces inside containment, horizontal as well as vertical, except for drops.
N ur ,,, 0.13(Gr tPr) '3 k
2 h,,,*(vfg)ita e , ira so Nu - -0.13 gP Pr '3 k < p, The term (Ap/p) is the difference between the bulk density and surface density, divided by the bulk density. Note that in this form the Grashof number with its i length dependence no longer appears and the heat transfer coefficient is dependent only on local properties.
ACRS 9/97 10 l
L Convection Heat Transfer ;
Correlations (cont.'j
[ 2 Laminar Free Convection Heat Transfer i
' Laminar free convection heat transfer is considered for the drops that result from the break liquid during blowdown, because their diameter is so small (~-10" ft.) that Gro << 1. For this case, Kreith presents the correlation for small j spheres:
h,,** d Nu r ,,, 2 k
ACRS 9/97 II
- Convection Heat Transfer <
Correlations (cont.}
r 3 Turbulent Forced Convection Heat Transfer The Colburn correlation was selected for turbulent forced convection in a channel-Nu r,m =
h'*d a
= 0.023Re o Pr '
k where the hydraulic diameter is two times the riser width. Turbulent forced convection occurs in the riser and downcomer.
ACRS 9/97 12
L Convection Heat Transfer r; Correlations { cont.}
4 Turbulent Opposed Mixed Convection The correlation for opposed turbulent mixed convection recommended by Churchill is used:
l Nmix = ( Nre , + N o ,c ) '
Using the correlations for free and forced turbulent convection, the mixed L convection heat transfer coefficient correlation is.
r 31/3 k (0.13d ) Ap h mix =_ Pro + (0.023) Re a2 Pro d (vfg) 2 p, ,
l Opposed free and forced (mixed) convection exists in the chimney where the l PCS natural circulation induces a bulk upward flow that is opposed by the negatively buoyant free convection on the cooler chimney concrete.
l i
ACRS 9/97 13
,..--- .--------- - - u Condensation / Evaporation Mass .
Transfer .
t L The heat and mass transfer analogy can be expressed as. !
Sh _fSc"I Nu ( Pr, so the Sherwood numbers corresponding to free convection, drop, and forced convection mass transfer are-r in Sh,,,,, = 0.13 OP Sco ,
t Ps
' Sc'
Sb"*P =4 < Pr ,
~
Sh o,ro m = 0.023 Re"* o Sc '
'ACRS 9/97 14 i
L Condensation / Evaporation Mass ; 1-
_ Transfer (cont.} .
Kreith defines the mass flux from the bulk gas to the condensing surface in terms of the mass transfer coefficient, k, as: '
ril " = k, M,, MAP,,m .
l where AP,,, = (P,,,,3oix- P,im,,,,). The Sherwood number is defined in terms of the l mass transfer coefficient, kg, and other parameters as:
L- Sh = k8R T L P'* *. '
Dy P where the log-mean air pressure is defined P im, ,,, = (P,i,,3oix- P oi,,,,1)/In(P,;,,3oix /
! Poir, ,,,). Combining these two equations with the appropriate mass transfer correlation gives the condensation or evaporation mass flux.
ACPOO97 15
! Rate of Change Equations E I l 4
I Paranneters Selected for Scaling AP600 Containment Pressure Rate of Change Location Normalizing Parameter i Equation Mass inside and Outside Break mass flow rate, ri1 9,3,x,o Containment Energy inside and Outside Break enthalpy flow rate, Containment ril o, ,,y oM ,,,,y ,
Pressure inside Containment Break flow work rate, T
Yo(1+Z )/(y-1)oril o,3,x,o P,,m/p,1m i
Momentum PCS Air Flow Path Buoyancy, Go i
ACRS 9/97 16
g.
- Mass Equation "
i i
dm _ g _ { g, dt l
. t E m,1 dm* . .
=K m.brx m g.brk
. + Em; m ,tm, f
i E 3 6*"
- where T= x,=m, xm, ,,x = 1 x ,3 =
g,brk,o bg.brk.o g,brk,o
- i l
i ACRS 9/97 17 1 i l
una em sua uma amm -aus suoi uma mas um sui um aus sum uma uma sus aun aus Mass Equation Steam and air mass and flow rate dimensionless variables are defined:
i,
- Containment gas mass m = mom*
L Containment gas volume V = VoV* !
. Containment gas density p = pop
- 1 Time t = Tt*
! Break steam flow rate s% y,
=
s,gori1*,,3,i l Break steam density p,,% =
p,%,op*,7 g
l Heat sink j steam flow rate ril,33 = m , ,3,om ,,3 1
i 9
ACRS 9/97 18 j
__--_.__-_a. - - - . . - _ _ _ _ _
. _- _ = _ . _ _ _ _ . _ _ _ . , . . . _ _ _ _ _ . _ _ - _ - , . - , . , . , , , , , ,
m.
i --
Energy Equation gm(u-ug}
, - %%-Nr) + e rn, - D%%-h,) + %(h -NT) n + hfg-T,)]
x %hik + x , P *rh,* - ((x,gQhM + x,,qriQh * + x,gh* T,*)
- a*f - x >
where: t au, P, Z,
e " %m, 3 Ke.bek
- I
- f. work * *m.f g i A h,g, a% 4,F-T,3,)
- %.N 3%
su , x-4 3%
.m , (g,3%
i i
ACRS 9/97 19
Energy Equation 1 Many of the mass and flow rate variables required to make the energy equation dimensionless were defined under mass scaling. Additional variables are defined:
Containment gas mass m =mm* o Containment gas volume V =Vy Containment gas density p = pop
- Break steam density p,, = p,,w.op*,3 Time t = T t* '
- Break steam flow rate s,m = s,,a.os*,x Gas intemal energy diff u-u, = Au,u* Containment gas mixture u - utro '
Break steam enthalpy diff h,x-h,,7, = Ah,woh *,3 Break steam h,-liquid h, at To Pressure P = P,P*
Heat sink j:
Steam flow rate s.3 =s ofo s*.3 Gas-film enthalpy diff h.3- h,y = Ah,,fo h*,,3h , of steam j - h, of inner film j i
Film enthalpy diff hy- h,,7, = Ah y, ,h*y h, of inner film j - liquid h, at T, Heat trans coef hy = hyy h *,3 radiation + convection (h,3 + hy )
i Heat transfer area A, = Ag A*,
Gas-liquid sud temp diff T-T y = (T - Ty),T*y 5
ACRS 9/97
_ _ . . ._ - - - . . - - , - ~ - - .. .,. . -- . - - _ _ _ _ _ . _ _ _ _ .
'M'M M M M M M M M M M H M -
M M M M
+
' 1 Pressure Equation
~
t i
i i
I f (1 +ZT ) dP *
- y(1 + Z T) P. ' T(1 +ZT) P ~ # y(1 +Z T) P.'
(y -1) ~d " 8" (y -1) p.,
(y-1) p, (y -1) p., YN I t
t I
ZT*V
- dP
- y*ZT* P * ..
- p.s .
,,,,,, h,*m m M + x,ge , ,
%+ x,y,, y*ZT*m, .P .
, l Tm d* Ye Pm Ym t ,
l l -El *p.weJNJAYJ * *p.=a*JSJ .ZT* P[*
+K paJh 5 ATf
( Ym Pm j where:
V, p,m, i
1 Pm.o
~ i, p,,,
P.
P. ,
them
- N " h- h.),(y -1), P.,
T y,(1 +Z ).
p., *p.sm.=om " l j
- rh,,, p .,, P. (y -1), p ,
- Kp.r Kp eJ - KmJ T,(1 +ZI), p ,(hmJ -hy, x,,% - xy e " th s.bm.ePr.o pme me (Y -1)e P"# h -
x,,q = T A(T-T),
Yo(1 +Z ),% P., i ACRS 9/97 21
i Pressure Equation ~
d i
Dimensionless variables used to make the RPC equation dimensionless are:
Containment steam mass .a , = m ,,,,m *,, .
i Time t = T t' Net liquid flow rate s r
=
$r.o5*r s;
Heat sink j steam flow rate = semy,6*.;
Heat sink surface area A, = Ag A,*
Containment to liquid surf temp diff (T-T,3) = (T-T,;)AT*,3 Combined rad + conv heat trans coef h, = h,,hy*
Cond/evap energy transfer coefficient h, = h ,,,h ,*
Effective energy transfer coefficient h, = h,,,h,*
i Gas volume V = V,V*
Break steam flow rate s,m = s ,%,os o *,.a Break-bulk steam enthalpy difference (h , m - h ,,) = (h, m-h,,)Ah*a
, Condensate enthalpy difference (h,,3 - h,,) =
(h,,3-h,,)Ah*,,j Bulk steam density p,, = p,
~
Compressibility function (1 +Z') = (1+Zp*Z ),q*
Specific heat ratio y = 7,7* ,
Specific heat difference (7-1) = (7-1),y*,
Total pressure P = P,P*
Steam partial pressure = P,,,,P *,, '
P,,
AcRS 9/97 22
'm m .m m m m M M M M M
- - ~
1 m +<
a Momentum Equation l
I 1
I.dm dt = G - R-IKEJ
. ds" xmv,m. i- =xmv, buoy G. -xmv,ms r- KE.
dt, 4
l i
Where V, Is o o Ro s*o j T= Kmy,m- = K mv, buoy = 1 Kmy,ms =
l QO Gto Go i l
l ACRS 9/97 23
t Momentum Equation e
i Tune t = t t' Volume V = V, -
' Inlet air flow rate rhi , = Q 'm Dowr(en er density pg = pgg*
Riser density pg =
pdd CL..ey density pg = pgg Inertia I, = I,I[where I, = IIw Mass flow rate rh = rho h*
i Buvy-r.cy G = G.G*
I Density p3 = p,pi* where p, = p, the ambient air density Flow resistance Rg = R R g*where R, = the total PCS loss Iis the gemr.eny dependent inertia vector: -
i 1 -((I./ A)2 , (UA)d , (UA)di) rh is the mass flow rate vector:
m = (mu,mg,meij G is the buoyancy defined by inig.tir.g the density times the dot product of the gravity and 41splacement vectors around a closed path:
ACRS 9/97 G =[pg ds = ,'pgdz+ pgdz+ pgdz+ 'pgdz , ,
g j S & d ds ent
! 1 t'
AP600 Phenomena Assessment -
i PI Values (WCAP-14845, Rev 2, Sect. 8,9)
ACRS 9/97 25
._ _ _____ ,_ _ ... _.....__ _ _ __ _ ____ _.____.__. _ ___ _.i
~
Heat Sink Surface Areas During r a:
Heat Sink Areas During DECLG and MSLB Transients (Units are ft*)
DECLG LOCA MSLB Peak Long Heat Sink Blowdown Refill Pressure Term Blowdown .
7 Drops 7.2x10 7.2x10 7 7.2x107 7.2x107 0 Break Pool 420 555 1933 1933 0 Steel 142,700 142,700 142,700 142,700 73,800 Concrete 22,600 22,600 22,600 22,600 22,600 l
l Jacketed Concrete 46,500 46,500 46,500 46,500 12,600 Evaporating Shell 0 0 47,613 27,000 0
- Dry Shell 52,662 52,662 3,600 24,077 52,662 l Subcooled Shell 0 0 1449 1586 0 ACRS 9/97 26
~
Mass Phenomena Pi Values ~
4
) Peak Pi Group Blowdown Refill Pressure Long Term MSLB ,
r, (sec) 39 985 913 5';73 537
- j. Contain- g,,, 1.31
~
1.27.' 1.30 1.22: 1.27 ment 11 .0 0 ' O.00* 1.00* 1.00 1.00 '
x,, 1.75 0.00 2.00 0.00 0.00 Steel x, m -0.05 .
-1.41 - -0.69 -0.02 -0.44 -
I Concrete xy -0.01 -0.08 -0.02 -0.09 -0.12 Jacketed x,3 -0.02 -0.46 -0.23 ~-0.18 -0.08 3
Evap xm,,, - -
-0.43 ' -
0.90 -
She!! x ,,,,, - -
-0.02 -0.89 . -
Dry Shell a, m -0.02 -0.61 - -0.03 -0.08 -0.37 :
- Refill was scaled with the same 200 lbm/sec flow rate used to normalize peak pressure.
Pi groups are normalized by different rates in each time phase. Values greater than 0.1 are shaded i for emphasis. Pi groups that are always less than 0.1 are not included.
}
ACRS 9/97 27 ,
~
Energy Phenomena Pi Values E Peak Pi Group Blowdown Refill Pressure Long Term MSLB
- T, (sec) 39 985 913 5173 537 Contain- x,,, 0.55
- 0.58 0.56- .0.63 0.58 ment x, l1.00 - 0.00* 1.00* '1.00 .1.00 i Steel x ,, , , -0.05 -1.35 i-0.64' -0.02 -0.44 Concrete x,,yy -0.01 -0.07 -0.02 -0.08 -0.12 Jacketed n ,,, -0.02 -0.44 -
0.21- -0.16 -0.07 Concrete Evaporating x ,, , ,, - -
-0.41 -0.81 -
Shell x ,,3,,,, - -
-0.02 -0.81 -
Dry shel! n ,.g 3 -0.02 -0.59 . -0.03 -0.07 -0.36
- Refill was scaled with the same 200 lbm/sec flow rate used to normalize peak pressure.
Pi groups are normalized by different rates in each time phase. Values greater than 0.1 are shaded for emphasis. Pi groups that are always less than 0.1 are not included.
l j ACRS 9/97 28
s 4
Pressure Phenomena Pi Values '
i Peak
- j. Pi Group Blowdown Refill Pressure Long Term MSLB l T, (sec) 39 985 913 5173 537 Contain- x,, 0.76i 0.76 .0.77 'O.76 0.76 x,,, 1.00- 0.00* 1.00* 1.00 1.00 Steel x ,y ,, -0.01 ' G.24 '
-0.09 -0.00 -0.09 xy. . .., -0.05 -1.41,. -0.69 -0.02 -
0.44 Concrete x,,,,,,,, -0.01 -0.08 -0.02 -0.09 -0.12 Jacketed x,,% -0.02 -0.46 : -0.23 -0.18 -0.08 Concrete '
. Evapora- ' x ,, ,, , - -
-0.43 -0.90 -
1 ting Shell i
Dry Shell x,,,,,,,,, -0.02 -
0.61 -0.03 -0.08 -0.37
- Refill was scaled with the same 200 lbm/sec flow rate used to normalize peak pressure.
Pi groups are normalized by different rates in each time phase. Values greater than 0.1 are shaded for emphasis. Pi groups that are always less than 0.1 are not included.
4 ACRS 9/97 29
I J
PCS Momentum Phenomena m
~
i Pi Group Blowdown Refill Peak Long Term Pressure PCS 70 Tg 61 15 7 Overall nm.,,, 0.13 0.13- 0.13 0.11 l
- xmy,3ooy 1.% . 1.% 1.% 1.n nmy m, 1'.00 1.00- 0.97 0.86 Downcomer u m,,oc 0.00 -0.05 -0.03 -0.16 Riser
- umy,g 0.48 0.52 0.46 0.58
~
Chimney x m,,, 0.52 0.53 0.58 0.58 ACRS 9/97 30 l
AP600 Phenomena Assessment 1 .
l l
4 i Model Prediction Comparisons l
l (WCAP-14845, Rev 2, Sect 8.6)
! ACRS 9/97 31 l
Steady State Equation p?
Comparison -
l Test r% ,dm*/dt* x,.,de*/dt* r h.,dp*/dt* Test r%.,dm*/dt* x..,de*/dt* ry,dp*/dt*
212.1A -0.197 -0.167 -0.104 218.18 -0.001 -0.001 -0.006 212.18 -0.076 -0.057 -9.034 219.i A 0.088 0.082 0.158 212.1C -0.048 -0.036 -0.022 219.1B 0.102 0.085 0.144 213.1 A -0.213 -0.185 -0.125 219.1 C 0.016 -0.001 -0.065 213.1B 0.022 0.039 0.101 221.1A -0.132 -0.117 -0.049 l
213.1 C 0.321 0.324 0.361 221.1B 0.080 0.089 0.044 , !
, 216.1 A -0.206 -0.173 -0.117 221.1C 0.106 0.098 0.075
^
216.1 B 0.068 0.092 0.103 222.1 -0.167 -0.158 -0.167 217.1A 0.141 0.142 0.157 224.1 -0.064 -0.118 -0.308 217.1B 0.115 0.115 0.123 224.2 -0.087 -0.106 -0.191 218.1 A 0.047 0.051 0.063 Average -0.004 -0.000 0.007 t
, Std Dev 0.133 0.128 0.147 ACRS 9/97 32
' ~
^
- Transient Pressure Equation ir j Comparison "
The scaling model was run using the peak pressures from WGOTHIC for an approximately nominal case for the four time phases. The resulting sum of terms from the right side of the pressure equation was transformed to dP/dt and
- compared to WGOTHIC. The transformation is dP/dt = dP*/dt* (P,/t). The scaled rate of pressure change equation without the unity value
- terms is.
i Np.t N p.g.brk,enth p.g,brk, work p,enthj p,qj
, p f, work p,workj i
- Containment Pressure Predicted by Scaling Model and WGOTHIC Peak Long Blowdown Refill Pressure Term s Scaling Model
- dP/dt +1.08 -0.12 +0.0019 -0.0042 (psilsec)
WGOTHIC: dP/dt +1.03 -0.02 +0.0066 -0.0050
- (psi /sec)
ACRS 9/97 33
l AP600 Phenomena Assessment i i i
i i
Dimensionless Parameters Range t
i (WCAP-14845, Rev 1, Sect 1,4)
\
i ACRS 9/97 34
! ! khi Dimensionless Parameter Range 1 Inside Containment Outside Containment ,
a Drho/ rho < 0.57 Re < 163,000 DPstm/Pim, air < 0.90 DPstm/Pim, air < 0.59
- 0.72 < Pr < 0.91
- 0.72 < Pr < 0.81
- Sc = 0.52 Sc = 0.52 ACRS 9/97 35
e-- W
~
l i
! a_ -
! Condensation Mass Transfer -
i i ,
l Tests: LST, Wisconsin y
! Parameter AP600 Range Test Range
- Drho/ rho < 0.57
l DPstmiP m,i air < 0.90 Sc = 0.52 _ _
ACRS 907 36
i
- Evaporation Mass Transfer 2 i
l Tests: W Flat Plate, Gilliland and Sherwood Parameter AP600 Range Test Range
~'
Re < 189,0C0 '
l DPstm/P m,i air < 0.59
, Sc = 0.52 - -
ACRS 9/97 37
~
l-----------------;
4 Air Flow Path Flow Resistance
! Test: Westinghouse 1/6 Scale,14 Sector
- Parameter AP600 Value Test Value Riser Re. 189,000 _
, i l
ACRS 9/97 38
Phenomena Assessment 5 4 Conclusions -
i The first ordar PI groups are condensation and evaporation Drho/ rho, DP3 dPim. air, Sc; Ree , DP3 dPim.ai, Sc, l
Imp,rtant components are Containment, riser, and chimney gas volumes Solid heat sinks and shell l
AP600 dimensionless parameter range is defined and adequately covered
- by the test ranges for Condensation l
l -
Evaporation ,
PCS air flow path resistance coefficient ACRS947 39
mas amm sua == amm um um um um ami aim una em
i
- iii b
, 1:
r i.
l l Containment Scaling l
Presented to the ACRS September 29,1997
- by:
W. L. Brown
- ACRS 9/97 4
_ :_ a _ ;; ;_ ;; ;;
INTRODUCTION isd ,
eIG
- Purpose of Scaling Scaling Process .
l T
Scaling i Transient (Blowdown) Phase Scaling O.uasi-steady (Long Term Cooling) Phase Scaling
- Conclusions Evaluation of Distortions L Sufficiency of Test Data Base i
l l ACRS 9/97 2
l i l .
Purpose of Scaling for AP600 y19 Containment Scaling used as tool to determine extent to which data from LST can be used for validation of heat / mass transfer correlations n computer code used to predict AP600 plant.
i
~
ACRS 9/97 3
i NI Ib5 Scaling Process .
i
- Define system to be scaled.
- Write goveming eqns. describing system.
- Normalize all variables in goveming eqns. using reference values which appropriately range variables such that they are of order 1.
Non-dimensionalize egns. by dividing through eqns. by coefficient of dominant term. -
- Identify resulting coefficients of egns. as Pi groups representing
~
phenomena. ~
- Numerically evaluate Pi groups for plant and scaled tests.
- Apply PI ratio distortion criteria. For this scaling analysis, 0.5<PI ratio <2.0 indicates sufficiently scaled phenomena.
l
' - Identify sufficiently-scaled phenomena and distortions.
ACRS 9/97
t a in t:1 Transient (Blowdown) Phase Scaling l I
! Rate of Pressure Change Significari;:
I I
t 5
f' ACRS 9/97 I_._ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _
a p Transient Phase System Definition .
U 5
l System includes: . .
l Break energy source which drives pressurization.
Containment atmosphere volume which provides compliance.
Internal heat / mass transfer sinks.
- PCS energy removal path not significant during this phase of ;
e 6
ACRS 9/97
4 Governing Eqns.
~
1 -
Conservation of Energy inside containment gas volume (l qn. 63) d(mu)* . .
- ]
,, = m,>,n h,,,, + { (m. s h.,, + m, , h,,,,,, ) - (m.,c., h,,.., + q, ) - F ,,
Equation of State inside containment gas volume (Eqn. 38) .
P Y = Zn R T
- Conservation of Mass inside containment gas volume (Eqn.57) dm - - - -
= ms,& + (ma ir,i + ms ,,,i ) - [ m,,,,,
g,
- Conservation of Momentum inside containment gas volume Containment t.reated as uniformly distributed (well mixed) at system level, therefore momentum / mixing not directly scaled.
7 ACRS 9/97
~~
s ini .
Rate of Pressure Change Eqn -
A P"6 00 Since global pressure response significant during transient phase, j scaling of containment atmosphere focuses on Rate of Pressure Change Eqn. (RPC).
Dimensional form of RPC Eqn. derived from combining conservation of Mass / Energy / State eqns. applied to well mixed containment control volume (Eqn.194):
dP , y P,,,,, ' y(l + Z') P (1 + Z') V = m " 'h' ' " - h" >1 + (l + Z ')
r -
+ mg (y - 1) dt _
y-l p,,,,, _ (7 -1) p, p' _ 7 ,
-[ m,{,,,,,(h;,,,,,, - h,,,,,) + y(1 ++h,,,A,T-Q,,,
2r)
J _
_ stm . _
ACRS 9/97 8
Normalization of RPC eqn. li variables ,
I i
Variables in RPC eqn. normalized as follows (egns. 195-207):- I P - P"'. " =
P - P"'. " .t y ;
dP* = AP'*/dP P* = pmax _p.mm gp"I t+= V*= i Tsys V,f r l
l 1 !
t 3 i
T h Pi I; m ,,,,,,'
(l + Z',) (l+ Z ) , ,.
(h, - h,,,,, ,1 =
i
, ' , - h,,,, 'I P=
m, * = ,
i p1 ~1 m,,, * = (l + Z,.h,,, {h,-h,,,,,[,
i 1
( 1 T = T' >
. 7 A.1 = ,
h'.,
s P'e, s
p " '
T - T,,,, , 7
r,**i4 y = f,,f 3)*
[-[ \ sim,,,
~ jl rer L
) ref ACRS 9/97 9
J
.i
'w Non-dimensional RPC Eqn. .
- Substituting normalized variables into RPC egn. and dividing through by coefficient of dominant term (break work term - 2nd coefficient on RHS of RPC egn), we obtain non-dimensional form of- !
RPC eqn (Eqn. 210):
i !
P c (1,
+ Z')
- V*dP*dt 2 , = x -mi.,
h,,,3.. (h, [1][n,;, Y * (1 + Z') * ".
" i x,1y - 1)
- ly - 1)
- p. ,,,
. y * (l + Z')' P
- r
+ x3mg , ,
- x, m rs.,L a h,,' - h,,,,, '
iy - 1,1
- p. ;
I i
. +
. T* l
- x, m ?m, y *(l + Z')
- Pstm ss , ,
s
- xA,.1T[ h,. - I',,,,
\ 1 - 1)
- ps,a-i 1 i ACRS 9/97
a i:
RPC Eqn. Scaling Ratios -
i
- - Comparing coefficients between AP600 plant and LST, following six scaling ratios are obtained (Eqns 217 -222)
t r
~
yy . - -
my P T pg (h,_ - h,,,,) ,
- p
, m,_ y
- y(l + Z') P_ -
P,,,
ll =-
": " g n, = . M P=_ m _L Pm . ,
y a, yy -
mf P Tsrs l (h ,_ - h,,,) p, P
,_ y ,,_ yzy + 7ry p,,,,,- - -
m p,,,,,
P a . ,, son _ (y- 1) p,,,,
_ , ,, _'~ p,,,,,
11 ACRS 9/97 w__ - _ _ _ _ _ - . _ - _ . - .
' 2' .i RPC Eqn. Scaling Ratios "
Scale ratios (cont'd): in ,,,,_
i-NI Kw _ gr R,
!!! star.
q.; j ~ of.;
b NKm_
stm 4gT _ 3ysno i
p,,,,, (T - 1) _ isr i
] = _- -
E 7 ;
4.) } l=) ) Ulsam) {N store ., ~ hsts
'e) 7 T
-$1 ~ Pst." (1 + 2 ) (T ~ I)-
arsoo $r"" (1 + 2') (T - I) Pst. . is7
[] * = c E*
1 i
j m,,,, (h,,,,, - h,,,,, )
r'~ (1 + 2 ) (r - 1) p,, _ ,,eoo 12 ACRS 9/97 s
i - - - == == = == = == = = == ==
Power to Volume (PN) and Power to Area F7 (P/A) Ratios for Time-Preserving Scaling AP600 If thermodynamic properties (P,T,p , T ) and time are preserved, I L a n d H ,6 " reduce" to simple Power to Volume (PN) and Power to Area (P/A) ratios, respectively, between AP600 and LST.
Power (P) refers to break. ,
- Volume (V) refers to containment gas volume.
Area (A) refers to heat / mass transfer surface area.
Tatrie 10-2 AP600/ LST Scale Ratios V (ft3)
LST 2,936 772 AP600 1,740,944 52662m Ratio
( (8.4)3 (8.26)2 Note 1. Represents shell area in AP600.
ACRS 9/97 N
Power to Volume and Power to l tir ,
1 Area Ratios -
- For Blowdown phase, based upon range of initial LST power levels: '
[ ply}
byi =[pfyj" = 5.0 to 25.0
- .For Quasi-steady phase, based upon range of long term LST power levels: ,
i l O R6 = ((P/A]j ~ 1.0 to 1.5 -
P/A I From property / time-preserving scaling perspective, LST Blowdown ,
phase is distorted, whereas, LST Quasi-steady phase is well scaled to the plant. -
14 ACRS 9/97
Dimensionless Rate of Pressure. it i Change Comparison Accounting for distorted time scale in LST Blowdown, si $.* vs.
non-dimensional time t
- for AP600 and LST is plotted using " fill" l system time constant definition of r,,, = f"" (revised figure 10-5):
m,-
07 Blowdown plase l
E e4 tar a2 00 .0 20 30 40 50 88 ACRS 9/97 _ty. = 23 sec
i!I $
- Transient Scaling Conclusions ' 2 Accounting for time scale distortion, AP600/LST comparison shows ;
similarity of scaled RPC egn. results in blowdown phase with respect to important phenomena related to source, sinks, and volume. ,
- Distortion exists in that refill!reflood phases not simulated in LST. .
Instead, LST has extended blowdown phase.
- Blowdown transient in LST sufficiently establishes proper range of ,
thermodynamic conditions inside containment for heat / mass transfer data use in long term cooling phase which is well scaled to the plant. 1
- l l
I l ACRS 9/97 l
l
3 l .--
yra 4
AP690 I
i
^
l4 Quasi-steady (Long Term Cooling)
Phase 1
- Rate of Change of Pressure Not Significant ACRS 9/97
- - ---- ------------l
- Quasi-Steady Phase System J j Definition -
System includes:
Break energy
! Condensation on inside of shell 1 Evaporation on outside of shell
- Subcooled heat transfer on shell Dry shell heat transfer
- Internal heat sinks are active but essentially saturated.
ACRS 9/97
gg, , ;g_g g g gg7 g gg, gggg
, 1 Quasi-steady Scaling Energy Eqn. Er u -
AP600 Non-dimensional form of energy egn. for containment gas (Eqn.
223):
i d(mu)
- K,,7. == K,,5g mh,ba b h$k + K,,,,_,, P
- ln}
g, ,
c
- . . 3
- E (K,,fg,,
q Ms m,j bh ,,,,j e + K ,y,j Msm,]bh V,j + K,,,,,h ,, A] AT},,,
i 1 -
Quasi-steady Energy Scaling p""ti
.^esoo Group Comparisons . .
' - Quasi-steady Energy Scaling group comparisons (Table 10-3):
Table 18 3 Emergy Pi Group Comparisen der AP6ee and the LST Predicted wish Scaling needel at 41.s psia
~
Calculated from Fi Group AP600 1.51
- II,m * -Km LST Data x,., 1.24 1.24 1.00 0 122 .
x, a 1.00 1.00 1.00 0 1.00 x,, g 0.00 0.00 0.00W 0 0.00 0.02 0.02 1.00m .0 0.03 x,,,,
0.91 0.93 1.02 -0E2 0.90 x,,g, m, g, 0.08 0.06 0.75m 0.02 .. 0.08 x, . 0.13 0.18 138 4.05 3 0.09 0.15 1.15 -0.02 0 09 x,,,,,, 0.13 0.67 0.62 0.92 0.05 0.74 x,,go, Note: (1) PredM using the measured air / steam concentrations, since the IST is not homogenous (2) fia = LST/AP600 (3) Pi group is not important because the psWM Pi group numencal value is smalt 20 ACRS 9/97
b 4
~ ' '
Quasi-steady Scaling Conclusions d i
Important phenomena well scaled between AP600 and LST(0.5 PI ratio < 2.0) during quasi-steady phase.
LST database sufficient for heat / mass transfer phenomena 1 validation.
- LST data can be used to examine known lumped parameter modelling biases in bounding evaluation model.
i ACRS 9/97 D
um ma sus em uma uma em num num en me uma em se amm um amm uns e
i l EVALUATION MODEL. REQUIREMENTS
'I t
'f
[
i i
t i
i
1 Introduction to Evaluation Model Development i
l 4
September 30,1997 ;
Presented by:
Joel Woodcock ACRS 947 1 i
M 4 = a ~- 6 w - "--h- --* ==---*-A-- _ - _. . . - - _ - -
- Introduction to Evaluation Model :
- Development -
l
. Outline DBA pressure Evaluation Model approach Evaluation Model requirements aligned with PIRT Validation process Conclusions l
l ACRS 9,97 2 t
- - - - . ._.. - - - - - - . . --- -- - - - - . , - - -- ---- ---- n -- - - - - - - _ - _
i -
i ,
- Introduction to Evaluation Model
- i Development -
j
~
i i
l l -
DBA pressure Evaluation Model approach j i
l f i
l l
l .
l l
l ACRS 9/97 3 i
_- - - _ _-.i_-_____ - __ _ _ _ _ _
Evaluation Model definition -
im r t
The Evaluation Model (WCAP-14812, Rev.1, Sect. 4.4) for AP600 containment pressure Design Basis Analysis ;
is the combination of the WGOTHIC code and methodo ogy for c eveloping input, for example:
Calculation of boundary conditions - for example, M&E releases (WCAP-14407, Rev.1, Section 4)
Bounding film stability (water coverage) effccis - methodology limits applied flow (WCAP-14407, Rev.1, Section 7)
Bounding circulation and stratification effects (WCAP-14407, i Rev.1, Section 9)
ACRS 9/97 4 i
l ! l l!!; i!;i!!l1l!l: i 5
a e
- s e u r i
e s
- n e s h r
s i
o n t p
e r
p
- t c o p s g i
s o n
- d e h i e
r r t g n d
- p e r n u
_ u i t o eM r
s s
e nb e a s
uE r e ,
s sg p pM d r
e eE e ein r m r e c pus u u yh
- l o
l et d ed v v n ro
- iev t n
i t
i a ts s p
t ap ef mo e s v ni r
e e e vlo r n n m e
c s s n s
_- e e o u r n o n i
ai u k v l o o n o p o s e t
n c t
v S i
S c mp n d o n y o s e
- o Cfu - - -
B c r 7
9
/
9 S
Cis - -
R C
A
,lllll . ;l !! !! ; j 1l ;l
- == sus sus sem um ums - aus - men - sem sum == mm == == == num Phenomena are treatec' in conservative containment '
. pressure DBA Evaluation Model (EM) t Phenomena models are included via internally programmed WGOTHIC code models, code input, and 1 supplemental evaluations to define relevant code input '
i !
Phenomena are treated conservatively for containment .
pressure DBA through Conservative input - for example, initial conditions supported by sensitivities to select the conservative direction i
Supplemental evaluations (external to the code) to obtain conservative pressure prediction, by selecting Code input to implement biases (example, correlation multiplier)
I imiting scenarios (example, circulation)
ACRS 9/97 6
l PIRT phenomena are treated to produce a conservative pressure response H and M phenomena are treated and bounded in the EM Many L phenomena are treated in the EM and most of those are j also bounded ;
WCAP-14812, Rev.1, Sect. 4.4 documents the EM approach taken for each PIRT phenomenon High level grouping structures the EM development
- Break source - Gas compliance - Initial conditions
- Condensation - Internal solids / pools - Evaporation
- - Convection - Radiant heat transfer - Film energy transport
- Baffle conduction / leakage
- Parameteric relationships among phenomena are identified ACRS 9/97 7
i - - - . . - _ .,, ,,, . , _ ,,,.
t Key phenomena relationships are used
- to structure model development
.. ........... y,
.- q .,
i .
Energy 11esistance ), .
. condan== nan 4 .
- i $
- l Convection . . .
t .
c' ,4
. M a' N l
. wmn ..- .
[
. shen ,
- u.n m .r Pressure aste ,
n*
a== como ofchange -
. .. oo =x
. *. Moor CNmney ,
- ** N Pe ;
enernd Heatsk*s dP , .
j; = de ,.
_-_ : u n .- : ::
(l ; .
~.
.i concrete @
j = =
Steel. W; l '
- 1. ::
Steeldacketed Concrete ;. ,
.. i L--- '-
internal E % nal .
Mornenturn harnenturn ACRS 9/97 8
.I Introduction to Evaluation Model
~
! : =
. =
Development -
Evaluation Model requirements aligned j with PIRT i
ACRS 9/97 9
Evaluation Model requirements aligned *
?
with PIRT . .
Internal containment volume
SUMMARY
OF EVALUATION MODEL ELEMENTS FOR HIGH AND MEDIUM PHENOMENA PlRT Phenomena / Code Element input Element Supplemental Parameters Evaluation Model Element Break source mass and Boundary Mass flow rate Approved SRP energy (1 A) condition end enthalpy methodology used tables - LOCA 6.2.1.3.2 i
- MSLB 6.2.1.4 !
Refill period conservatively neglected '
Gas compliance (2C) Gas properties Volumes EM conservatively initial conditions minimizes free volume and uses, worst case initial conditions based on sensitivity studies Initial conditions inside (4A, Initial conditions initial conditions: Sensitivities used to 48, 4C) temperature select bounding humidity direction (WCAP-14407 pressure 5.2-5.5)
ACRS 9/97 1d
, . s ------ ------
Evaluation Model requirements aligned :
'f with PIRT Heat sink conduction (internal & containment shell) & pool PIRT Pheiiomena / Code Element input Element Supplemental Evaluation Paramwers Model Element Containment solid heat EM conservatively minimizes sinks (3), shell (7), and available heat sink surface ;
Pool (5) area and properties (WCAP-14407 Table 4-107)
Internal heat sink 1D conduction Solid heat sink Mesh established consistent conduction (3D,7F) and solutions material with Biot number heat capacity (3E,7G) properties and mesh _
Heat transfer through Model not Operating deck and ,
horizontalliquid films invoked compartment floors not (3C) included in model so no >
additional penalty needed !
Pool condensation / Liquid phase Pool node WCAP-14812 4.4.5A, and evaporation (58), interfacial mass elevations f WCAP-14407 4.7.1.1 shows transfer lumped pools are modeled to maximize heat source to Pool circulation / Lumped liquid containment gas stratification (SA), and phase .,
Pool conduction (SE) ?
- ACRS 9/97 II
- - ---- ~----.-------
Evaluation Model requirements aligned ? ?
with PIRT Intemal mass transfer PfRT Phenomena / Code Element input Element Supplemental Evaluation Parameters Model Element Cordensation mass transfer PCS mass PCS: input PCS correlations validation (3F,58,7C) transfer multipliers (WCAP-14326, Rev.1) l
! correlations Uchida-Revaporization
_Uchida correlation Break source direction Break source Circulation and stratification and elevation (18), elevation node evaluation (WCAP-14407, Momentum (IC), and (momentum and Section 9. Table 9-1) density (1D) direction not relevant in lurrped parameter)
Circulation and Intemallurrped Intemal noding AP600 range of parameters stratification (2A) node-network diagram and studied:selectlimiting solution junction circulation pattems; introduce parameters stratification bias intercoirpiniment flow Intemal flow path (28) data andloss coefficients Source fog (2D) Droplet field Boundary WCAP-14407 Sensitivities to:
equations condition fraction - thermal effec.s (5.8) of Iquid input as - circulation effects (9.A) drops ACRS 9/97 12
Evaluation Model requirements aligned 59 with PIRT External mass transfer PIRT Phenomena Code Element input Element Supplemental
/ Parameters Evaluation Model Element !
Evaporation mass PCS mass transfer PCS correlation PCS correlation
. t ansfer(7N) correlation multiplier validation (WCAP-14321)
Lumped parameter PCS natural Extemal noding 1/6 scale hydraulic test circulation node-network Loss coefficients of 14 degree section (9A,13A) solution (WCAP-13328)
Conservative loss coefficient Uquid film flow Liquid film tracking Applied PCS flow Film stability evaluation rate (8A), model rate to limit WGOTHIC Water PCS water credit for evaporative i temperature temperature cooling (WCAP-14407, (8B), Film Wetted fraction and Section 7) stability (8C) wetted perimeter at each elevation i ACRS9S7 13
=
Evaluation Model requirements aligned * =
with PIRT External liquid film, external heat transfer, and baffle l PIRT Code Element input Element Supplemental Evaluation Phenomena / Model Element Parameters _
Uguid film Uguid film No userinput energy transport tracking model specific to this (7E,7M) item Convection heat PCS heat transfer PCS correlation PCS correlation validation transfer (3G,7H, correlation multiplieron shell (WCAP-14326) 10A,108,14A) surfaces Radiation heat View factor Emissivities for transfer (3H,71) radiative heat surfaces exchange model Environment for annulus ambient surfaces temperature Baffle 1D conduction Baffle properties conduction solutions Flow path (10D) and Baffle modeled across leakage paths baffle (10G)
ACRS 9S7 I4
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Validation process for features that differ -
l from operating plant database L
! Shell heat and mass transfer - WCAP-14326, Rev.1
! Water coverage - WCAP-14407, Section 7 l
Operating plants do not rely significantly on heat removal to environment through containment shell An experimental database used to develop bounding model for l film stability to limit credit for evaporative heat removal
! Circulation and stratification - WCAP-14407, Section 9 1
l Operating plants inc!ude fan coolers and sprays which enhance
- homogenization of the containment atmosphere
- Available larger-scale integral system experimental database considered ACRS 9/97 17 8
w - - -
m - . ,- , - --- - - - - . - - , ,
L Shell heat and mass transfer Heat and mass transfer experimental database
- and parameter ranges discussed in earlier
! presentation .
Experimental database is used to Verify applicability of selected correlations over AP600 ranges Select a bounding value "or EM multiplier on heat and '
mass transfer correlations for the shell !
- - ----.a------------ ~ -
Water coverage experimental database "
WCAP-14407, Section 7 Range of nondimensional groups is adequately covered for AP600 r -
The water coverage experimental database includes
- full-scale sector of dome with 10 feet of sidewall several smaller scale heated tests (including film dryout) sketches and videotapes of LST through complete dryout Experimental database is used to develop a model for coverage, which is limited by film stability considerations, and the resulting evaporation rate l
provides input to EM via an " applied flow" that limits the EM evaporative heat removal iteration is made with EM for consistent heat flux values ACRS 9/97 19
Circulation / stratification experimental 1 =
database (WCAP-14407}
Nondimensional groups (9.C.1.3) considered in developing AP600 physical model Experimental database (9.C.2) includes Separate effects cavity tests (9.C.1) used to develop 5-region ,
representation of AP600 containment (9.C.1.4) 1 BMC, CVTR, NUPEC, HDR facilities which are used to draw
~
integral system conclusions w.r.t. circulation / stratification (9.C.2)
LST used to investigate means to bound effects of LP biases (9.2)
Evaluations external to code, and sensitivities using LP
,g ere j h ustifiable, used to develop bounding approach ,
l ,l , ilil!II :l l! l! IIl!
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1 The test databases for important phenomena support
! development of a conservative EM Models for phenomena and processes have been selected, for a conservative EM, using:
Models internally programmed in WGOTHIC
- Biases specified with conservative WGOTHC input l i
Supplemental evaluations to derive biases i
- EM approach bounds volume and dominant sources and
! sinks, which yields a conservative containment DBA l pressure prediction ACRS 9/97 22
i l .
~
Validation of AP600 Correlations .
- Evaporation Mass Transfer L Condensation Mass Transfer PCS Air Flow Path Flow Resistance Convection Heat Transfer i
L i
i l
ACRS 9/97 1 l
i.
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Evaporation Mass Transfer ~~
Mass Transfer Data from the Westinghouse Wet Flat Plate Test a,b I
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.i I ACRS 9/97 2
Condensation Mass Transfer ~
,4 4
Mass Transfer Data from the LST and Wisconsin Tests
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i Test: 1/6 Scale,14o Sector
- i Measured K = 2.4 at Re = 105,000 i
l Using K = 4.3* at Re = 189,000 i .
l
- Minor design modifications increased 2.4 to 2.5. Apply 30% margin 1 !
! 1.3 x 2.5 = 3.25. Add full head loss for baffle design change over '
dome 3.25 + 1.0 = 4.25. .
l l
ACRS 9/97 4 l
(, , ______;g__gy_g_gg-- - . - -
l Convection Heat Transfer Turbulent free convection with 0.73 multiplier is
- used on shell inside containment l
l Uchida is used on other internal heat sinks l -
Assisting turbulent mixed convection with 0.84 j .
multiplier is used on shell outside containment Assisting turbulent mixed convection with no i
bias is used on baffle and shield building ACRS 9/97 5
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- Circulation / stratification data base ?'
Y overview and conclusions -
Outline How experimental data base is used to develop lumped i
parameter (LP) bounding approach l
Documentation of bases j Overview of integral containment test facilities and experimental I data base in the literature Summary of LP containment codes experience List of LP biases and capabilities Summary of how LP biases / capabilities are addressed in EM Conclusions i
- Note: Unless noted, (references) are ACRS 9/97 0 seC60ns in EM-W@, Rev.1 2
l-------------------j l
l i
l Circulation / stratification data base
.: 5 Overview and conclusions -
l l ;
How excerimental data base is used to deve op ,
lumped parameter (LP) bounding approach i
I l
1 ACRS 9/97 3 1
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l base usage ;
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The data base supports the development of a ,
l bounding treatment for circulation and l stratification in two principle ways:
! AP600 extraaolation and expectations to develop a
- physical representation of effects on concentration p fields }
1
- Development of methods to use the WGOTHIC lum aed parameter for a bounding Evaluation Model 1
ACRS 9/97 5
1
- Circulation / stratification data base 3 "
l i
overview and conclusions L
1 i
l Documentation of bases for EM treatment i
l of Circulation / stratification
- i' 1
i f
ACRS 9/97 6 i
L Circulation / stratification bases 5
- documentation summary Data from the literature are documented i
4 AP600 5- region physical model based on separate effects enclosure tests - 9.C.1 International test facilities and experimental data base overview -
. 9.C.2
- Published international LP containment codes experience and
!- derived biases and capabilities - 9.C.3 t
Westinghouse AP600 EM is documented ,
! Circulation / stratification guidelines for applying WGOTHIC for the EM - 9.1.2, 9.2.4
(
ACRS 9/97 7
" "E Circulation / s': ratification data base overview and conclusions Overview of integral containment test facilities l and experimental data base in the literature i ACRS 9/97 8
4 ..
- International integral containment test experimental 1" l data base covers a range of scales i
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- LST BMC NUPEC N HDR AP600 i
I ACRS957 9
- - ---= ---- ----
Integral containment test facilities and !
-?
l experimental data base in the literature j
Important dimensionless groups (9.C.1.3)
- Applicable to discussion associated with building up AP600 physical model based on enclosure tests L
Collectively, the experimental data base (Table 9.C-1 and 9.C-2) includes ranges of
- Break size (large/small) - Release location
- Heat sink types - Volume, height I
- Release of noncondensibles - Number of compartments l - Initial and boundary conditions ACRS 9/97 10 1
L _ -- . -
WESTINGliOUSE PROPRIETARY CLASS 2 9.C-61 1
- Table 9.C 1 Comparison of Various Facilities Facility LST BMC NUPEC CVIR HDR AP600 Volume m3 83.1 640 1300 M28 11300 48710 (used)
Height m 6.1 9 17.4 34.7 60 57.9 thameter m 4.57 11.25 ~ 0.8 17.7 20 39.6 Number of 3 9 25 3 62 72 11 Compartmentr, Volume of the 79 % 70 % 41 % 44 % 81 %
dome Containment steel concrete steel concete steel shell steel shell Walls concrete and concrete and steel steel 5
I I
I I
I I
I I
I Development of Expected Flow Patterns July 1997 0:\3(K4w 9c.wpf:11: 4 /2497 Rnision 1
9.C-62 WESTINGHOUSE PROPRIETARY CIASS 2 a
l Table 9.C-?
summmmmmm - -
Overviewed Tests from International Database muummmmmmmmmmumummmu Position of the Release Point and Strat!!ication or Facility Experiment Mairi Feature Other Relevant Data Circulation I BMC F2 set First Phase stepwise steam addition release point is high Hr/Ht=0.444 circulation t:eough the majority of compartments, I external innulus stratified I BMC F2 set Phase 2 inducing the natural circulation with steam steam release point is low Hr/Ht = 0.111 circulabon through the majority of compartments, I injection extemal annulus stratified BMC F2 set Phase 3 heater on in R6 to heat source location circulation through I reverse circulation is low Hr/Ht = 0.111 the majority of compartments, extemal annulus I stratified BMC F2 set Phase 4 steam injection in steam release point is circulation through R6 compartment low the majority of Hr/Ht = 0.111 compartments, external annulus stratified BMC Test 2 hydrogen low position of hydrogen uniformly I Two compartments (Phase 1) injection, uniform initial tempe~ture, hydrogen source Hr/Ht = 0.06 distributed, circulation present I orifice pre:,ent, low feed rate BMC I Test 4 Two compartments hydrogen injection, uniform initial high position of hydrogen source Hr/Ht = 0.57 concentration stratification occurs I (Phase I) temperature, no orifice BMC Test 6 hydrogen low position of stratification present, Two injection, stratified hydrogen source highest hydrogen compartments initial Hr/Ht = 0.06 concentration in the (Phase I) temperature, lower compartments I orifice present I Development of Expected Flow Patterns July 1997 o;\3006w4cwpt1Mrn497 I
Revisaon 1 t
,.- ,,, ---,--e
WESTINGHOUSE PROPRIETARY CLASS 2 9.C-63 l O Table 9.C-2 Overviewed Tests from International Database (cont.)
umummmun mummmmmmmmmmmmmum - mmmmmmmmmmmmmmmmmmmm nummmmmmmmmmmmmmmmmmu Position of the Release Point and Stratification or Facility Experiment Main Feature Other Relevant Data Circulation l
E BMC Test 12 hydrogen injection high release point hydrogen uniformly Six compartments in R2 room (high), H,/H, = 0.69 distributed, I (Phase II) uniform initial temperatures circulation present I BMC Test 20 Six compartments (Phase II) hydrogen injection in R6 room (low),
stratified initial low position of hydrogen source H,/H, = 0.06 stratification present, highest hydrogen concentration in the temperature lower compartments BMC RX4 sump heat up low podilon of the circulation present, and three heat and hydrogen homogenization of hydrogen source temperature and injectio,s H,/H, = 0.0 concentrations I NUPEC M4-3 simulated break inside the low steam generator low position of the heat and hydrogen source circulation present during release, temperature stratifies I compartment, steam and Hr /H, = 0.0 and concentration homogenizes after hydrogen release, the end of release containment shell I- insulated I CVTR First test without the intemal water sprays steam release in the upper compartment, high position of the steam release H,/H, = 0.525 temperature field stratifies concrete shell CVIR The second and steam release in high position of the temperature field third test with the upper steam release stratifies internal water compartment, H,/H, = 0.525 but not as strong as sprays concrete shell in the previous case HDR E11.2 high positioned high position of the stratification. exists, release point steam release extenud sprays (small break) H,/H, = 0.55 promoted circulation ,
and active external spray I
I Development of Expected Flow Patterns July 1997 o:\300t=-9c.wpf:1b.072497 I
Revision 1
9.C 64 WESTINGHOUSE PROPRIETARY CLASS 2 B
Table 9.C-2 T'
Overviewed Tests from International Database (cont.)
- muummmmmmmmmmmmmummmmmmmmmmmmmmumm -
Position of the Release Point and Stratification or Facility Experiment Main Feature I _
HDR E11.3 low positioned Other Relevant Data Circulation global circulation small break pattern formed I closed spiral stairway entrance I HDR E11.4 lev ;> 4tioned re tec ,aint (snadl bicak) low position of the steam release H,/% = 0.18 global circulation formed almost uniform I and active extemal spray temperature distribution except below release point HDR T31.5 simulates DBA high position of the temperatures and gas large LOCA in the steam release concentrations first
,I upper section of H,/H, = 0.526 stratify the :ontainment and latter homogenize HDR V21.1 simulates DBA middle position of Equal heating of both large LOCA in the the steam release staircases first middle section of H,/H, = 0.38 suppressed the contamment circulation. Slight (in both staircases) global circulation
_ _\ was generated later.
HDR E11.5 simulates DBA low position of the global circulation large LOCA steam release due to the steam in e lowest H,/H, = 0.18 release, gas mixture section of the injection and sump I containment with effects of dry boiling contributed towards heat release and homogemzation sump boiling I
'I I Development of Expected Flow Patterns July 1997 I
o:\3006w.9c.wpf:lt>C2497 Rninon 1
l Summary of experimental basis ,
9 Experimental findings, based only on interpretation of test data, are documented in 9.C.2 for each facility
- BMC, NUPEC, CVTR, HDR Interpretation of results using available data for pressure and generally including T, V, C stm, C air , fields Indication of magnitude of thermal and/or concentration l gradients above-deck and top-to-bottom in containments Circulation between compartments generally can be inferred from other data; some velocity measurements are also available ,
ACRS 9fJ7 15
l -------------
~ ^
W---
l l i I il
~
l Summary of experimental basis ,
Application to AP600 L
Identifies physical situations which may lead to stratification with large gradients or non-circulating regions AP600 dead ended compartments have vents on top Remainder of AP600 containment will experience circulation Supports basis for stratification gradient to assess for AP600
- Confirms AP600 physical model (9.C.1) based on separate effects tests
- Provides basis for judging acceptability of a LP parameter model with respect to predicted circulation pattern
- Will be covered at December 11-12,1997 meeting ACRS 9/97 16
em en == == == == = == == == am == == mm == == == ==
t Overall conclusions regarding vertical stratification T
. gradients ,
In containments with global circulation loops Difficult to develop and maintain a stably stratified containment volume l
Unless experimenters deliberately changed the configuration or operating conditions to achieve stable stratification -
i Magnitude of temperature differential in above-deck regions is ~10oC top te bottom of containment with break in lower regions is ~250C -
Application to AP600 -
Choice of extreme gradient used in EM stratification assessment .
confirmed with data from larger scales ACRS 9/97 17 1
, , ,,,,y,,yyy;gga;;;
~
Summary of global circulation conclusions'
- 19.2.4} ,
l 1 l
Buoyancy causes plume to rise through ceiling of compartment receiving break flow 1
^
Global circulation loop develops, closing with t'
entrainment into break compartment 1
Application to AP600 Provides qualitative criteria for reasonable circulation pattern when using LP model for sensitivities to i various break positions i
t ACRS 9/97 18 1
4
1 :
Summary of conclusions (9.C.2.5) ,
11 of 20 experiments have low release position
- (H/H <0.2) and may be compared to AP600
1 l
7 BMC -
1 NUPEC (M-4-3) 3 HDR Remainder of experiments provide supporting evidence for AP600 physical model derived in 9.C.1 based on enclosure tests l
I ACRS 9/97 19
~ ' ~ '
L--- ----- ---- ----
Summary of conclusions (9.C.2.5} (cont.} ~
i Of the 11 relevant tests,9 have global circulation through the dome which contributes to homogeneous temperature and concentration fields -
I The 2 with low-elevatin releases where stratification is recorded 1 had special boundary conditions
- BMC test 20
- initially stratified concrete walls (and air) temperature l field by pre; heating the Upper region for several days; source is H 2 l only .
l NUPEC hl-4-3: due 10 the insulated shell, temperature field stratifies l at end of the seiease period, although injected gas homogenized l slowly even after release stopped l
l ACRS 9/97 20 i
um an as an = == == == == == == == == == == : ==
Summary of conclusions (9.C.2.5) (cont.)
Application to AP600 Global circulation in the AP600 will be promoted by External cooling of the shell by PCS water Hot concrete structures positioned in the lower portion of the containment after the LOCA blowdown High kinetic energy of a release e
ACRS 9/97 21
, .ams sus num man mas num sus aus man am num num uma em um num uma mas am j . .
Summary of conclusions (9.C.2.5) (cont.}
7 experiments with low kinetic energy releases at high location
]
(H/H,> 0.5) - 2 BMC,3 CVTR,2 HDR 6 with both steam and hydrogen injection show thermal stratification BMC test 12 - due to uniform initial temperature field boundary conditions and circulation patterns formed by hydrogen injection, the concentration field was uniform i CVTR test 2 and 3 - internal sprays decrease pressure and vertical temperature gradients
- HDR tests E11.2 and T31.5 - temperature and concentration fields j stratify at the beginning of experiments, continued global circulation decreases the vertical gradients 4
HDR E11.2 - additional steam release in the lower compartment and application of external sprays promotes global circulation and ACRS 9/97 decreases Vertical gradients 22
- - - - . - - - - - - - - - - ==
i 4n Summary of conclusions (9.C.2.5) (cont.) 1 A review of the tests indicates that enhancement of global circulation, and thus atmosphere homogenization, will occur if:
- 1. The position of the steam or hydrogen release is low (H/H <0.2)- .
1
- 2. External sprays applied (promotes circulation in cooled region)
- 3. Internal sprays are active
- 4. Opening between ccmpartments are large
- 5. For concrete heat sinks bounding the upper region, the temperature field is not initially stratified
- 6. Heat sources, such as hot concrete walls or a sump, are at the low positions
- 7. Compariments are connected (not dead-ended)
ACRS 9/97 23 i
i i a Summary of conclusions (9.C.2.5) (cont.) .
4 Application to AP600 ,
In the case of AP600, most compartments are relatively open and designed to prevent dead regions
, where pockets of H 2 could accumulate A bias is applied to heat sinks in dead-ended compartments j in the EM by disabling heat sinks after blowdown For circulating compartments, the noted conditions (except #3) are satisfied for LOCA, enhancing homogenization i
ACRS 9/97 24
Circulation / stratification data base !,! n,!
overview and conclus. ions Aesoo e
Summary of LP containment codes l
- applied to international data base i
ACRS 9/97 25
I International LP experience app ied to 1 .
AP600 containment EM development
! Participation in and review of international containment exaerimental data base anc ISP LP exercises has led to definition of 9 LP code biases and capabilities understanding of important differences in WGOTHIC LP formulation Experience served as a basis for 4
examining LP biases using the integral WGOTHIC model of LST **
i determining whether global circulation patterns in LP sensitivities
- are reasonable **
- Note: Items which will be discussed ACRS 9/97 26
i Summary of LP containment codes !!n!,
applied to international data base Aesoo Lumped parameter containment codes applied in international standard problems (OECD-sponsored,13 organizations,10 countries)
- ISP-35 NUPEC Test M-7-1 and M-4-3 *** (for example)
- - MELCOR 1.8.2 - JERICO
- CONTAIN 1.12 - RALOC
- COMPACT - MAAP 4.0
- FUMO - WGbTHIC 1.0
- - WAVCO
- Note: NUPEC M-4-3 was provided as a test case for initial ccde model setup before the blind prediction for M-7-1. M-4-3 was natural circulation, without internal containment sprays (9.C.2.2)
ACRS 9/97 27
I e
I N Table 5-1 List of participants Organisation Country Code used Code Experts Dr.Snoeck, Jean I Belgium HELCOR 1.8.2 TRACTEBEL TRACT Ms.Auglaire.
Michele UK CONTAIN 1.12 AEA AEAUK Mr.0'Mahoney, Bob COMPACT NNC Ltd. Dr.Coe, Ian M Italy FUMO University Pisa PISAI Prof.Oriolo, Francesco Dr.Paci, Sandro I CONTAIN 1.12 CEC.JRC JRCEC Dr. Jones. Alan Ms.Bonanni. Elena Switzerland VAVC0 PSI PSISV Mr.Megaritils.
Georg Dr.Duco I france JERICO CEA.IPSN/DPEI IPSNF Dr.L'Heriteau, Jean-Pierre l
Mr.Bardelay, Joel i Cermany RALOC CRS G**GE Mr.Scwinges Bernd Mr.Heuttermann, Bernd Finland RALOC IVO IV0FA Dr.Lammila, Eari l Netherlands MAAP t. 0 KEMA KEMAN Mr.Stempniewicz, Marek Mr.Bakker, Peter !
USA CONTAIN 1.12 SNL SNLUS Dr.Eltavila Dr.Basu, Sudhamay Dr. Stamps, Douglas I WGOTHIC 1.0 DOE /Wei tinghouse WESUS Mr. Woodcock, Joel Mr.Ofstun, Rick Japan CONTAIN 1.12 JAERI JAERI Dr.Sugimoto, Jun MRI Mr.Singo, Ueno I
I I 5-18
~
---f-- ~-- --
Benefits of participation in/ evaluation 01 : =
International Standard Problems Westinghouse exercised WGOTHIC on HDR Westinghouse participated in ISP 35 (NUPEC)
Discussions with other code users / developers via telecons and ISP 35, and review of documentation OECD ISP models included a varying number of connected lumped parameter nodes in the above deck region and generally one or two nodes per compartment below deck (see figure on page 22) l Various methods to attempt to overcome the lumped parameter code biases were presented by participants of the ISP meetings Attempts to overcome the LP bias with input such as loss coefficients were unsuccessful ACRS 9/97 29
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ACRS 9/97 31
- ;E !
List of LP biases and capabilities Published experience with lumped parameter containment codes can be summarized in terms of 9 biases and capabilities (9.C.3.4) 1.** Network of volumes were not adequate to represent stratification-2.** Sump liquid level and sump temperature were not well predicted 3.** Some codes ... missing or over simplifying buoyancy terms 4.** To account for recirculation flows, ... used double junctions in the horizontal direction 5.** For releases low in containment LP mod,els predicted ;
well: pressure, temperature, and helium concentrations in circulating ,
compartments l
poorly: temperature and helium concentration in dead ended compartments
- Note: Items which are relevant to i ACRS 9/97 i
, , ,, ,, o o o 1 u r
List of LP biases and capabiities .
6.** Scenarios with homogeneous containment atmosphere can be simulated successfully with lumped parameter models. (Such
! conditions typically result from breaks located within the bottom 20 percent of the containment height.)
- 7. Circulation effects due to sump boiling (releases generated at the bottom of containment) were well simulated
- 8.** The order of magnitude of computed internal velocities and trends in flow direction match data; ho aever, predicted internal velocities differ by as much as a factor of two [ ,
I (a,c)
- 9. LP method does not have the capability to predict hydrogen distribution in a stratified containment atmosphere with high-positioned
Circulation / stratification data base 'i overview and conclusions -
1
! i 1
l Summary of how LP biases / capabilities are addressed in EM l
l' i
ACRS 9/97 34
,,,,,ww.g,,,,gywwww i
The methods for addressing LP biases and iF capabilities are summarized in 9.1.2 o
The following. slides are a look-alead at the EM approach to support agreement on the test data base sufficiency, providing:
An overview of the methods used to address each relevant item-A summary of the EM approach. and Pointers to relevant EM documentation Discussion of AP600 containment pressure DBA EM anc specific biases will be presc.ited December 11-12,1997 ACRS 9/97 35
== - -- -- -- - ==-
i Network of volumes were not adequate to 9
- 3 represent stratification- LOCA (item 1)
~
stratification effect assuming 3-regions, relative to homogeneous volume, is studied using hand calculations (9.3.1.3,9.B)
Experimental data base is used to define an upper bound for AP600 vertical concentration gradients A bounding gradient (Xsim = 0.98, 0.63, 0.28) is selected for-further study Comparing totalintegrated heat removal from a homogeneous volume compared to a stratified volume with 3 regions leads to the biases implemented in the EM Within LP below-deck compartment (CMT room example)
Within above-deck region ACRS 9/97 36
l Stratification biases applied in EM '
~
CMT room rising plume => bias by removing
- compartment floors to bound the effects of stratification
~
- Calculation showed that homogeneous volume without floors underestimated net heat removal l relative to stratified 3-region calculation Bias is applied to below-deck circulating compartments, including sensitivity cases with various assumed buoyant source locations ACRS 9,97 37 i
~
Stratification biases applied in EM T q'LOCA & MSLB} - Above-deck _
- Above-deck region => bias by disabling heat and mass transfer to operating deck floors in EM Calculation showed negligible (<0.5%) net effect between homogeneous volume and 3-regions Calculation conservatively neglected increased evaporation with increasing shell temperature in top of 3-regions In spite of no indicated penalty, a bias is conservatively applied to above-deck region in EM.
ACRS 9,97 38
Stratification biases applied in EM and -
5 j bases (LOCA & MSLB}
Disabling heat sinks is conservative relative to rate bias i; Time constant indicates that heat sinks which were ]
removed would still absorb heat prior to peak.
pressure if they were credited in EM l-i t
! ACRS 9/97 39
Network of volumes were not adequate to s .*
represent stratification- MSLB (item 1)
In addition to biases derived for LOCA, stratification is-imposed in MSLB EM (9.4.2) 1 LST 222.3 (3 in. source-up), 222.4 (3 in. source-horizontal) l indicates kinetic energy would drive significant circulation below j source j
- LP dissipates momentum within a node, so there is no kinetic. j energy-driven circulation below the EM break node i l EM places break at LP node above operating deck to conservatively minimize circulation below deck
]
ACRS 9/97 40 1
l j"
1
[ Sump liquid level and sump temperature *.. _
were not well predicted (Item 2)
[ Sump nodes selected to maximize sump as a i
heat source {4.7.1.1)
I l
i ACRS 9/97 41 l
i
-_. - . _ - - . - . . ____-__..---J
1 Use of double junctions (related to '5 5 items 3 and 4) i -
Use of double junctions in EM documented in 9.2.4 l
l i
1 g1 #2 Makes use ofMOMC l junction hydraulicpressure l head between two ends witlun i a volume
- Figure of merit is circulation patterns predicted.by WGOTHIC in each LOCA sensitivity study compared to global circulation inferred from experimental data base Experimental data base provides indication of expected AP600 circulation Figures in 9 show consistency of WGOTHIC circulation with data base ACRS9S7 42
~
For releases low in containment : : -
(AP600 LOCA} ptems 5 and 6)
LP model predictions were good for pressure, temperature, l and helium concentrations in circulating compartments
- LOCA
- EM used for sensitivities, with momentum postulated to be l dissipated, to various postulated break locations at cold leg (low) elevations LOCA: EM sensitivity performed for un-dissipated jet case by crediting only the estimated improvement in heat and mass transfer MSLB: Bias addressed by comparison to~ test data with high kinetic energy, and selection of break node to impose stratification (9.4.2)
ACRS 9/97 43
For releases low in containment ~:.
(AP6QO LOCA} 9tems 5 and 6) q' cont.)
- LP model predictions were poor for temperature and helium concentration in dead ended compartments LOCA: bias by disabling heat sinks in dead ended compartments after blowdown phase ACRS 9/97 44
em em . em
- _ _ - - .-== == == - == == - == == == == == == - ==
Order of magnitude of internal velocities match data; * *E predicted velocities differ by ~a factor of two (/ tem B)
Only free convection is credited on inner s irfaces in the EM; thus, the pressure calculation is independent of calculated internal velocities
- Therefore, internal forced convection benefits are
- neglected when they exist during
! LOCA blowdown
! MSLB (see WCAP-14326, Rev.1, Section 3.9, Figure 3.9-5) l I
i i
j ACRS 9/97 45
. _ _ -- o
-. - - - - - - == - - - - - - - - m.
Topics for December 11-12,1997 meeting B~N ;
- Confirmation of LP biases and limitations with LSTintegral model
- Description of scenarios and assessment of pressure effects ;
- Justification of use of LP for specific sensitivity cases Results of sensitivity cases Selection of limiting scenarios Stratification penalty assessment (9.B)
Data providing basis for AP600 range of stratification (9.2.1 - 9.2.3,9.C.2) i
- Choice of bounding vertical gradient Homogeneous versus 3 region results 4
ACRS 9/97 4s i i
- i i
i Circulation / stratification data base ;
- L i
overview and conclusions i
l i
n l
VOnclusIOnS i
I ACRS 9S7 47 i
i
sum aus e uma mas amm en amm uma amm nas uns uma num um sum um man ame I
i} S in m
uonclusions 2 l
Experimental data base has been identified to address circulation and stratification phenomena 4
A sufficient range of scales is included 1
LP biases are consistent across the range of scales Method of applying LP biases to AP600 developed using
- WGOTHIC model of LST matrix tests Methods to address lumped parameter code biases and capabilities conservatively are applied for the WGOTHIC Evaluation Model A meeting has been scheduled for December 11-12,1997, to '
discuss the WGOTHIC containment pressure DBA Evaluation Model l ,
ACRS 9/97 48
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AP600 PCS Test Program Summary l Supplemental Information in support of l ACRS Thermal-Hydraulic Phenomena Subcommittee Meeting on .
l Westinghouse AP600 Passive Containment System TAP l September 29 & 30,1997 1 l
i i
l 9/16/97 1 i
- Presentation Objective .
- For the Large Scale 'est (LST) and Separate
! Effects Tests (SET), summarize; j Test Objective
! Test Design Test Instrumentation l Range of Test Parameters to the extent necessary to support use of the l data in the development of AP600 containment Eva uation Model 9/16/97 2
j:
Separate Effects Test Summary i Phenomenon Tests l Univ. of Wisconsin
! Condensation W Large Scale Test I Gilliland and Sherwood l Evaporation W Flat Plate
! Hugot Eckert and Diaguila Convective Heat Transfer Siegel and Norris W Dry Flat Plate W Dry Large Scale Water Coverage and Stability W Water Distribution System, l LST, SST, Wet Flat Plate PCS Loss Coefficient W 1/6 Scale Test Environmental Interaction University of Western Ontano Wind Tunnel Test
. 9/16/97 3 s
L l Full-Scale Water Distribution Tests !
c 1 L
(WCAP-13960}
l -
Test Objective: :
i- i Provide full-scale demonstration of capability to i
- distribute water on containment dome and top of ,
I sidewall with worst-case manufacturing i
Test Design: i l
1/8 sector of full-scale dome l
maximum allowable weld tolerances built-in coated with inorganic zinc .
L -
Range of Test Parameters:
- Applied Water; [ ]8c 9/16/97 4 t
Full-Scale Water Distribution Tests "
(WCAP-13960}
i l Photograph of the Test Rig is i
proviced on the following page.
i i
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{WCAP-13960) l l
L Photograph of water distribution boxes and weirs is given on following page.
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- STC Wet Flat Plate Tests
~
4 (WCAP-12665 Revision 1) l Test Objective:
, Obtain data on evaporative mass transfer and dry surface heat transfer ;
! Observe film hydrodynamics including liquid film
- coverage, film stability and formation of dry patches Test Design: .
i l heated plate; [ ]c Coated with inorganic zinc l
Two orientations; vertical and [ ]a,c from vertical l Air duct formed by clear plexiglass cover 4
l j 9/16/97 7 i
. . _ - - . _ _ _ _ - - _ _ _ _ . _ - . - __.--_--___-I
l STC Wet Flat Plate Tests i c
! {WCAP-12665 Revision 1} _
Test Loop Schematic ,
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9/16/97 10
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i
i STC Wet Flat Plate Tests .
=
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Range of Test Parameters:
l Applied water flow from: [. : a. c to: a. c
[ t Initial temperature of applied water from: [ la. c 2 L
to: [ 1a. c Average Heat Flux
- a. c i
from: [:
to: : Ja. c 9/16/97 i - - - - _ - ------
Small-Scale Tests l>~
- Test Objective:
Mass transfer data over range of operating conditions l 1
Included severe accident conditions
> Test Design:
Pressure vessel [ ] diameter Air annulur. of [ ]o c formed by I
transparent baffle Uniform wavy film on outside surface formed by simple weirs 9/16/97 12
l Small-Scala Tests -il.i "i
{WCAP-14134'j -
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~
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Ranges of Primary Test Parameters:
Steam supply ac steady state (maximum)
[
ja, c peak transient
~
l [
i l External shell cooling air flow l
Natural convection i
i -
Forced convection to [ ]c Applied water film Reynolds number range; [. ]o. c t 9/16/97 14
m . . _
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Large Scale Test (LST}
i i
Test Objective: For a geometrically-similar pressure
! vessel with natural convection and steam condensation on interior and evaporation on exterior of vessel, obtain
- the following data;
! Condensation mass transfer l Water coverage j i t l Film stability i
- Dry external shell heat transfer i
Above-deck circulation and stratification I
i
} 9/16/97 15 1
w_ __ . _ _ _ _ _ _ - _ _ - _ _ _ . . .._ .. . _ _ _ . . :
4 E
i I l Large Scale Test 'LST} !
l Test Design:
l 1/8 scale pressure vessel surrounded by a i
transparent air annulus baffle enclosure Film created by evenly spaced J-tubes.
1 i
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9/16/97 16 1
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Forced convection to [ .
i Applied water film Reynolds number range; [0 to 470]8.c He!ium concentration;
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- -9/16/97 22 1
University of Wisconsin 1 Condensation Tests -
Test Objective:
i Condensation heat transfer i
Liquid film heat transfer i
, .i 9/16/97 23
University of Wisconsin y; Condensation Tests -
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9/16/97 24 i
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Condensation Tests -
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Condensation Tests -
L Range of Test Parameters:
Gas Velocity; 3 to 10 ft/ser Steam Partial Pressure; 0.24 to 0.78 :
l =
Mixture Temperature; 160 to 210oF i
l l
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9/16/97 27 i
! i
'i W 1/6 Scale Test .
Test Objective:
Measure form losses associated with PCS air flow Test Design:
1/6 scale model of a 14o sector of following;
- inlet
- downcomer
- l riser chimney Fan driven air flow at Re = [ ja, c 9/16/97 28
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9/16/97 ' 30
..--- -- ---T- -
University of Western Ontario '
Wind Tunnel Test
- Test Objective:
Examine potential for wind-induced flows in riser /downcomer I Provide design information
! - Test Design:
1:96.67 scale model of containment building Other plant structures included.
Turbine Building Cooling Tower Pressure measurements at specified locations 9/16/97 31
~
University of Western Ontario n
- Wind Tunnel Test - - -
AP600 Model in Wind Tunnel with
[ Upstream Terrain Model
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- 4. _ _ - . __ _ .__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ !
4 L University of Western Ontario L Wind Tunnel Test -
l Instrumentation Schematic, Typical-
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1 9/16/97 33 A -- . _ _ __m_ e__ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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University of Western Ontario Wind Tunnel Test Range of Test Parameters:
With and without surroundings Chimney opened and closed, smooth and rough l
Reynolds numbers
! - Chimney [ -]ac ja, c
- Main Building [
34 9/16/97
Additional Heat Transfer Tests and .
their Test Objectives -
- Chun and Seban
- Hugot Turbulent mixed convection Evaporating wavy laminar heat transfer and turbulent liquid film l
heat transfer
- Siegel and Norris Turbulent mixed convection Gililand and Sherwood heat transfer Turbulent forced convection evaporation
- Eckert and Diaguila mass transfer Turbulent mixed convection heat transfer 9/16/97 35
~
l .
t PCS Test Program Summary '
Reviewed the tests that provided supporting data for the AP600 containment pressure DBA Evaluation Model correlations i
Additional tests that provided the basis for conservative inputs and modeling approaches are discussed with those topics (e.g., circulation and stratification) 9/16/97 36