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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20138A2041997-03-31031 March 1997 Pre-SALP Rept for SALP Period 960225-970906 ML20199G7191997-01-28028 January 1997 Rev 0 to Grand Gulf Nuclear Station Engineering Rept GGNS-97-0002 for GL 96-06 Evaluation of Drywall & Containment Penetrations ML20141A1321996-07-31031 July 1996 Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr ML20115A5851996-06-20020 June 1996 GGNS Engineering Rept for Evaluation of Ampacity Deratings for Thermo-Lag Fire Barrier Encl Cables in Fire Areas/Zones OC214,OC302,OC308 & 1A539 ML20108D0861996-04-30030 April 1996 Surveillance Specimen Program Evaluation for Grand Gulf Nuclear Station ML20115A5831996-04-18018 April 1996 Engineering Rept for Evaluation of Ampacity Deratings for Thermo-Lag Fire Barrier Encl Cables in Fire Areas/Zones OC202,OC402,OC702 & 1A316 ML20100J8621996-02-22022 February 1996 Engineering Rept Safety/Relief Valves Safety Function Lift Setpoint Tolerance Relaxation Summary Rept ML20094M5241995-11-20020 November 1995 Self Assessment SALP Period 940227-960224 ML20078S1351995-02-0808 February 1995 SWS Operational Performance Insp (Swsopi) for Ggns ML20072C9891994-04-30030 April 1994 Survey of Melcor Assessment & Selected Applications, Third Draft ML20063H7791993-12-31031 December 1993 1993 Self Assessment ML20046A2601993-06-18018 June 1993 Safety Sys Functional Assessment, Low Pressure Core Spray & RCIC Sys. ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20116K8001992-11-13013 November 1992 Quarterly Status Rept for Period Ending 920930, 'Degraded Core Accident Hydrogen Control Program.' ML20095K0951992-04-30030 April 1992 Resolution of High Groundwater Levels at Grand Gulf Nuclear Station ML20086K4741991-10-31031 October 1991 Cycle 6 Plant Transient Analysis ML20086K4991991-10-31031 October 1991 Cycle 6 Reload Analysis ML20086K5111991-10-31031 October 1991 LOCA Analysis for Single Loop Operation ML20086K5191991-10-31031 October 1991 Nonproprietary Siemens Nuclear Power Corp Grand Gulf Unit 1 Reload XN-1.3,Cycle 4 Mechanical Design Rept Suppl 1 ML20029C3461991-03-31031 March 1991 Simulator Certification Rept for Grand Gulf Nuclear Station. ML20073K8451991-03-31031 March 1991 Entergy Nuclear Performance Rept,Mar 1991 ML20043B6871990-03-31031 March 1990 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Jan-Mar 1990 ML19353B1281989-12-0101 December 1989 Number 1 Low Pressure Turbine Rotor Ultrasonic Insp Summary. ML19332D1691989-09-30030 September 1989 Quarterly Status Rept for Jul-Sept 1989 Degraded Core Accident Hydrogen Control Program. AECM-89-0165, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 8906301989-06-30030 June 1989 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 890630 ML20235X2621989-02-28028 February 1989 Criticality Safety Analysis of Grand Gulf Nuclear Station Unit 1 Spent Fuel Storage Racks W/Gaps in Neutron Absorbing Panels ML20235N3271989-02-22022 February 1989 Rept on Evaluation of Torsion Shear Stress Components in Design of Pipe Supports ML20247B1901988-11-30030 November 1988 Revised Flow Dependent Thermal Limits AECM-88-0021, Degraded Core Accident Hydrogen Control Program, Quarterly Rept Covering Period 871031-12311987-12-31031 December 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Rept Covering Period 871031-1231 AECM-87-0163, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Apr-June 19871987-08-27027 August 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Apr-June 1987 ML20065N4861987-04-30030 April 1987 Flux Wire Dosimeter Evaluation for Grand Gulf Nuclear Power Station,Unit 1 ML20214U1711987-03-31031 March 1987 Technical Rept 86.2GG, Verification of Individual Plant Evaluation for Grand Gulf. W/Jr Siegel 870313 Release Ltr AECM-87-0102, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending on 8703311987-03-31031 March 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending on 870331 AECM-87-0015, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 8612311986-12-31031 December 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 861231 ML20213G2221986-11-10010 November 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 860930 ML20151A8791986-09-30030 September 1986 Rev 1 to SPDS Safety Analysis ML20215L2311986-09-30030 September 1986 Rev 0 to Grand Gulf Nuclear Station Safety Relief Valve Fatigue Evaluation ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20199L1091986-04-0303 April 1986 Station Blackout Evaluation Rept,Grand Gulf Nuclear Station ML20207G6991986-03-31031 March 1986 Feedwater Heaters Out-of-Svc Analysis,Grand Gulf Units 1 & 2 ML20155B0911986-02-28028 February 1986 Single Loop Operating Analysis ML20205J7381986-02-18018 February 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 851231 ML20141N8871986-02-13013 February 1986 Metallurgical Evaluation of Recirculation Piping Ctr Cross Surface Cracking Following Induction Heat Stress Improvement,Grand Gulf Nuclear Station - Unit 1, Final Rept L-09-100, Rev 0 to MPL-09-100, Grand Gulf In-Plant Safety Relief Valve Test Fatigue Evaluation Final Rept1986-01-31031 January 1986 Rev 0 to MPL-09-100, Grand Gulf In-Plant Safety Relief Valve Test Fatigue Evaluation Final Rept ML20137E4471985-11-19019 November 1985 Metallurgical Evaluation of Recirculation Piping Ctr Cross Surface Cracking Following Induction Heat Stress Improvement,Grand Gulf Nuclear Station - Unit 1, Interim Rept 1999-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20209J1961999-07-12012 July 1999 Special Rept 99-001:on 990528,smoke Detectors Failed to Alarm During Performance of Routine Channel Functional Testing.Applicable TRM Interim Compensatory Measure of Establishing Roving Hourly Fire Patrol Was Implemented ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20209G0691999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear Station.With ML20206Q4831999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Grand Gulf Nuclear Station Unit 1.With ML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205P8771999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207K5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20207A8301998-12-31031 December 1998 1998 Annual Operating Rept for Ggns,Unit 1 ML20206R9501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20206D7721998-12-31031 December 1998 South Mississippi Electric Power Association 1998 Annual Rept ML20198E2481998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20195F4121998-11-13013 November 1998 Rev 16 to GGNS-TOP-1A, Operational QA Manual (Oqam) ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195C2791998-11-0505 November 1998 BWR Feedwater Nozzle Inservice Insp Summary Rept for GGNS, NUREG-0619-00006 ML20195F4801998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K2391998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Grand Gulf Nuclear Station Unit 1.With ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20153B2161998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20237B6661998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Grand Gulf Nuclear Station,Unit 1 ML20236R0231998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Grand Gulf Nuclear Station,Unit 1 ML20155J0811998-05-31031 May 1998 10CFR50.59 SE for Period Jan 1997 - May 1998 ML20249B1251998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Grand Gulf Nuclear Station,Unit 1 ML20248B6261998-05-11011 May 1998 Rev 6 to Grand Gulf Nuclear Station COLR Safety-Related ML20217Q6701998-05-0606 May 1998 SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating Cycles ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20247F3591998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Grand Gulf Nuclear Plant,Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20217P0381998-04-0606 April 1998 Safety Evaluation Supporting Amend 135 to License NPF-29 ML20217A0291998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Grand Gulf Nuclear Sation,Unit 1 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20216J2021998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Grand Gulf Nuclear Station,Unit 1 ML20203A2891998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Grand Gulf Nuclear Station ML20247B4111997-12-31031 December 1997 1997 Annual Financial Rept for South Mississippi Electric Power Association ML20203H9741997-12-31031 December 1997 1997 Annual Operating Rept, for Ggns,Unit 1 ML20198P1121997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Grand Gulf Nuclear Station,Unit 1 ML20203B5581997-12-0404 December 1997 Special Rept 97-003:on 971111,valid Failure of Div 2 EDG Occurred,Due to Jacket Water Leak.Failure Reported,Per Plant Technical Requirements Manual Section 7.7.2.2 ML20203K4031997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Grand Gulf Nuclear Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20199F3431997-11-18018 November 1997 SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 1999-09-09
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Text
r p wm ~d ATTACHMENT 2 AECM-82/574 Flow Science, Inc.'s Evaluation Report on Modified SOLA-VOF CODE 9
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) ttutonkeau 9B 132s Rusty Die la Alemcs Airw Aerxko 87544 Kriephew (SM) 662-2636 EVALUATION REPORT on MODIFIED SOLA-V0F CODE October 18, 1982 For: Grand Gulf Nuclear Station Humphrey Containment Concerns Prepared by 60'U./ ' 5 Cyril W. Hirt J L#fA tes M. Sicilian l
Subject:
Grand Gulf Nuclear Station Humphrey Containment Concerns Evaluation Report on Modified SOLA-V0F Code Flow Science, Inc. has reviewed the findings presented in the G.E. Design Review Report: Effects of Local Encroachment on Pool Swell, dated 9/24/82. At the request of Mississippi Power &
Light Company, we have prepared the following additional comments concerning our evaluation of the Design Review Report and of the applicability of SOLA-V0F to pool swell phenomena.
- 1. Basic Capability of SOLA-V0F The SOLA-V0F code has been used for a wide variety of fluid dynamic applications. Its capability for solving incompressible flow problems with free surfaces has been demonstrated through
- numerous comparisons with analytic and experimental data.
Documentation of these comparisons is given in the following references:
- a. B.D. Nichols, C.W. Hirt, and R.S. Hotchkiss, "SOLA-V0F:
A Solution Algorithm for Transient Fluid ? low with Multiple Free Boundaries," Los Alamos Scientific Laboratory report LA-8355 (1980) [see pp. 44-58 and pp.
l 108-117].
i b. C.W. Hirt and B.D. Nichols, "A Computational Method for Free Surface Hydrodynamics," ASME Jour. Pressure Vessel Technology, 103, 136 (1961).
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- c. B.D. Nichols and C.W. Hirt, "Hydroelastic Phenomena in Boiling Water Reactor Suppression Pools," Proc. 5th International Conf. on Structural Mech. in Reactor Tech. , Berlin, W. Germany (1980) .
- d. B.D. Nichols and C.W. Hirt, " Numerical Simulation of BWR Vent Clearing Hydrodynamics," Nuc. Sci. Eng., H,196 (1980).
- e. C.W. Hirt,Institute Research B.D. Nichols, and L.R.(1981 report NP-1856 Stein} Electric Power Vol. 1 : " Numerical Simulation of BWR Suppression Pool Dynamics,"
Vol. 2: " Multidimensional Analysis for Pressure Suppression Systems,"
Vol. 3: Studies of Bracing Influence on BWR Pool Swell Dynamics."
References c - e contain the most relevant data comparisons for pool swell phenomena.
- 2. Assumptions in SOLA-V0F SOLA-V0F providos a numerical solution algorithm to the Navier-Stokes equations (mass and momentum conservation equations). These equations assume incompressible water and only consider viscous stresses associated with a constant coefficient l of viscosity (i.e., no turbulence is included). There should be no question of the suitability of the differential equations.
The Numerical Solution algorithm is based on a well established finite-difference method that has been used and refined over a period of 17 years (J.E. Welch, F.H. Harlow, J.P. Shannon, and B.J. Daly, "The MAC Method," Los Alamos Scientific Laboratory report LA-3425, 1965).
The principal limitation in SOLA-V0F solutions is that they 2
. s cannot describe phenomena whose scales are less than the size of the underlying finite-difference grid. This, of course, is the basic limitation of any numerical solution method. For pool swell phenomena this limitation has an important consequence related to bubble breakthrough times. Breakthrough is known to be enhanced by small scale Taylor instabilities. For water, the dominant unstable wavelength is on the order of a centimeter, which is far smaller than the smallest mesh cell used to model the pool region. By not allowing this small scale penetration to occur, the SOLA-V0F calculations will have delayed bubble breakthrough times. Consequently, bubble pressures, which remain above the wet well pressure until breakthrough, will accelerate the pool surface to a higher velocity in the calculations than in a real case. This, therefore, is a conservatism. Some of this conservatism has been reduced in the G.E. calculations because they include a model for breakthrough which ramps the bubble pressures to the wet well pressure at a time determined from test data. It should also be noted that three-dimensional bubbles will break through sooner than two-dimensional bubbles (see below) so this too is a conservatism in the SOLA-V0F calculations.
3 Effect of 2D versus 3D Bubbles on Pool Swell Che two-dimensional, axisymmetric bubbles modeled in SOLA-V0F are slower to break through pool surfaces than spherical 3
bubbles with the same pressure history. The reason for this is evident from a simple 2D, cross-sectional picture of the two cases:
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1 *b CASG 33 CASE In the 2D Case the top water layer will accelerate upward uniformly (assuming no variations normal to the page) and no breakthrough will occur! In the 3D Case fluid will be accelerated most above the top of each bubble (where the fluid layer is thinest). Fluid will also be pushed left and right above each bubble center, allowing the bubbles to deform and push through the surface as shown schematically here:
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Bubble penetration accelerates in time because the amount of water to be accelerated above the bubble is continually reduced.
The net upward fluid momentum will also be less- in the 3D 4
Case than the 2D Case because the horizontal area on which the bubble pressure acts is less in the 3D Case.
From these examples it is clear that increasing the surface curvatures of bubbles will increase their ability to penetrate the pool surface. Therefore, we see that bubbles generated in Mark III suppression pools by multiple inlet vents will more readily penetrate the pool surface than an axisymmetric bubble at the same pressure and located the same distance below the surface.
By the same argument, the distortion of an axisymmetric bubble by a limited encroachment will induce local curvatures that can lead to earlier breakthrough.
The influence of bubble pressure on pool surface velocity can also be understood from the above picture. The vertical velocity acceleration above the center of a bubble is primarily l the result of the local pressure gradient and gravity accelerations. The average pressure gradient is the difference in bubble pressure and wet well pressure divided by the thickness 1
of the water layer. Thus, higher bubble pressures (or smaller water layers) produce larger pressure gradients, hence, larger upward accelerations.
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- 4. Influence of Steam Condensation By the last argument, any steam condensation thet would reduce bubble pressures would also reduce the upward l 5
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accelerations, resulting in amaller pool swell velocity.
Therefore, assuming equal mass flow rates through the vents, flow with some steam versus a pure air flow will result in lower bubble pressures and lower pool swell velocities.
, l 5 Deflection of Pool Surface by Encroachment 0
In calculations with a 360 encroachment the paol surface is significantly tilted from the horizontal with its outer ed6e ,
( i .e. , at maximum radius) much higher. This feature is a direct consequence of the deflection of the flow by the bottom of the-encroachment. Fluid trapped between the bubble and the encroachment is forced to move radially outward as'the bubble -
grows. Thic radial momentum persists as the fluid rises and ,
causes the pool surface to tilt as observed.
- 6. General Electric Modifications to SOLA-V0F A basic assumption used in G.E.'s modification of SOLA-V0F is that bubble preasures are uniform within the bubble. 'This assumption is acceptable when the fluid interfaces are moving at speeds which are slow compared to the speed of sound in air.
Because water / air interface speeds in these problems are at worst ,
a few tens of feet per second, this condition is satisfied by a ,
fair margin.
Not having to compute gas flows within bubbles is a grer;t .
simplification, for then it is only necessary to follow the time dependence of global bubble properties such as total gas mass and 6
total volume. G.E.'s implementation of these global properties is based on standard gas dynamic relations connecting different gas states. Their formulation based on pressure drop, stagnation conditions, computed volume changes, and standard ideal gas relations is logically correct. We have not reviewed the actual programming of these relations into the SOLA-V0F code. Also, we have not reviewed the prescribed dry well pressure history nor the flow loss used at the vents.
The G.E. staff has performed extensive comparisons between their modified code, SOLAV01, and test data from 1/9,1/3, and full-area-scale test facilities. These data comparisons provided an operational procedure for the scaling of code results with data. That is, the code had to be run in rectangular geometry to properly model vent clearing, and bubble volume corrections were based on pool area ratios. There is no way to rigorously justify 1
these procedures, but the data comparisons are quite good and provide confidence in the method for the type of problems considered.
- 7. Summary The weakest point in the G.E. study is still the point at which bubbles are assumed to coalesce so that bubble pressures can be ramped from the 360 0 encroached case to the case with no
(
! encroachment. This was the one Open Item reported in the Design Review Report. Bubble growth and coalescence is a strictly 7
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three-dimensional phenomena, which cannot be directly modeled with SOLAV01. It is this feature that has required the introduction of volume correction factors and other model approximations. Under the two-dimensional limitations of the SOLA-V0F code, the G.E. analysis has been well done. Extensive data compariuons have been made with tests having no encroachments that provide an operational procedure for how to run and interpret SOLAV01 calculations. By combining the 360*
encroached and unencroached cases-into a composite model G.E. has constructed an approximation of pool swell behavior under actual plant conditions. Bubble pressures are computed using the 3D corrected bubble volumes (smaller volumes), but these pressures -
4 are applied in the 2D bubbles. Both effects should enhance pool swell velocities (i.e., higher bubble pressures and a more coherent water layer over tlie bubbles). Thus, these model approximations give conservative estimates for pool swell.
It's somewhat harder to judge whether the bu%1e pressure ramping procedure is conservative or not. Using the 360*
encroached case pressure out to t = 1.0s is conservative because a higher pressure generated undet a limited encroachment will tend to be relieved through azimuthal expansion. On the other hand, the selection of 1.0s as the time to start ramping down the pressure and the total ramp time of approximately 0.05s is an engineering judgement for these parameters. The assumption is that bubbles generated at different vents will coalesce at 1.0s 8
- e. o and thereafter have the same pressure. Near the encroachment, however, higher pressures may slow bubble growth and coalescence.
Unfortunately, this flow region is strongly three-dimensional and a priori estimates are difficult to make.
To go beyond the present model would necessitate fully-three-dimensional calculations. Such calculations would eliminate the need to introduce 3L bubble volume corrections and the need to select a time for ramping bubble pressures between the full and unencroached cases.
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