ML20010D697

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Slide Presentation Entitled, Code Improvements
ML20010D697
Person / Time
Issue date: 07/07/1981
From:
Advisory Committee on Reactor Safeguards
To:
Shared Package
ML20010D695 List:
References
ACRS-1877, NUDOCS 8108310025
Download: ML20010D697 (8)


Text

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TRAC-PWR RELEASES CODE 7/80 7/81 7/.82 1_2/83 IMPROVEMEl;TS PD2 PF1 PF1/ MOD 1 PD3 REFLOOD MODELLING X1 X2 x3 DYl;AfilC GAP CONDUCTAI1CE X

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DETAILED GAP (FRAP)

X4 IMFROVED 1/0 Af;D GRAPHICS X5 X6 MASS CONSERVAT1011 X

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i C0l;DEiSAT101; MODELLING X7 X

NON-C0i' del SABLE GAS X

X8 RC-FLUID, 1-D COMPONENTS X

TWO-STEP !!UMERICS X 9 X 10 i

IMFROVED TRIPS X 11

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IMPROVED C0:TROLS X12 k

13 STEAM GENERATOR MODELLING X

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IlGRIZ01TAL SEPARATED FLOW X 14 REACTIVITY FEEDBACK X

X15 X 16 DORON TRAllSPORT X

EALANCEOFPLAi!TCOMPONENTS X17 TIE-PLATE CCFL CORRELATION X18 CHOKIfiG MODEL X

X20 19 SEC0 lid LIQUID FIELD X 21 L:STRIBUTED SLAB C0llDUCTANCE X 22 23 24 PRESSURIZER VALVE MODEL X

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MULTI-DlMENSIONAL KINETICS g.

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INPROVEMENTS MADE IN THIS CODE VERSION IMPROVEMENTS MADE ON PREVIOUS CODE VERSION, IF NECESSARY 1

X FOOTNOTES EXPLAINED ON. SEPARATE PAGE p

0D10831002S 810724 i

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I FOOTNOTES TO CODE IMPROVEMENTS 1

MOVING flNE MESH 2

HEAT TRANSFER AND CORE EnTRAINMENT 3

HFAT TRANSFER AND CORE ENTRAINMENT (c0NTINUED) 4 SPECIAL FRAP VERSION ALREADY DEVELOPED BY INEL 5

GRAPHICS 6

I/0:

SEE SEPARATE SLIDE 7

NRC CONDENSATION WORKSHOP RECOMMENDATIONS 8

AIR DIFFUSION SEPARATE FROM STEAM 9

1-D:

SEE SEPARATE SLIDE 10 3-D 11 SINGLE AND MULlIPLE SIGNALS j

12 INTEGRATORS AND DIFFERENTIATORS 13 SPECIFIC GE0 METRIC FEATURES PRE-PROGRAMMED DH/Dz FLOWS 14 DUKLER MAP FOR SEPARATED FLOW:

p 15 BORON FEEDBACK 16 MULll-DIMENSIONAL FEEDBACK 17 SPECIFIC COMPONENTS PRE-PROGRAMMED 18 IMR0VED MODELLING FROM INEL/GE: IDL DATA 19 INEL MODEL 20 SMALL-BREAK DATA, IF AVAILABLE 21 INCLUDES UPPER PLENUM DE-ENTRAINMENT MODELLING 22 GIVES SLOWER WALL HEAT RELEASE THAN LUMPED PARAMETER MODEL 23 TMI 24 ATWS m _

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LOFT TEST PROGRAM Effective July 1,1981 Tenta tive

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Test ID Commitment Date Description L3-3/L9-1 4/22/81 Small hot leg break experiment.

Loss cf all feedwater.

. Scram on high pressure - delayed.

CV Leak 7/22/81 Required test of containment leak Test integrity.

L6-7/L9-2 8/24/81 Simulated turbine trip.

Multiple failure continuation of L6-7.

L5-1/L8-2 11/16/81 Intemediate size break (accumulator line).

Core uncovery at high decay heat level.

Replace A2 1/26/82 F1 center fuel pressurized to With F1 350 psi.

L2-5/L6-6 4/8/82 200 percent cold leg break at 50 MW to' produce the worst probable core themal hydraulic conditions.

k No fuel damage.

Boron dilution transient.

L6-8 (LA-10) 6/16/82 Operational transient, contingency.

L9-4 (LA-3) 10/7/82 ATWS, Loss of Offsite Power.

L3-8/(LA-9) 12/2/82 Small break, primary coolant pumps L8-1A on, contingency.

L5-2 (LA-2) 1/22/83 Intermediate break, contingency.

l 0 L9-3 2/26/83 ATWS, Loss of Feedwater Replace F1 4/27/83 F2 pressurized bundle.

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l L2-6 7/21/83 200 percent cold leg break at 50 Kd.

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LOFT RESEARCH INFORMATION LETTERS IN PROCESS 1.

AliTICIPATED TRANSIENT L6-1, L6-2, LG-3 AND L6-5 PHENOMENA EVALUATION 2.

SMALL BREAK LOCE'S L3-0, L3-1, L3-2 AND L3-7 PilEN0F.ENA EVALUATION l

3.

SMALL BREAK PREDICTION CAPABILITIES 4.

LOFT LOCE'S L3-5 AND L3-6 PUMPS OFF/0N RESULTS 5.

COMPARIS0N OF NUCLEAR AND ELECTRICAL R0D RESPONSE FOR LARGE BREAK PWR LOCA CONDITIONS 6.

RESULTS OF THE AUGMENTED OPERATOR CAPABILITY PROGRAM 7.

LOFT TECHNICAL SUPPORT CENTER DEVELOPMENT 4

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LOFT INSTRUMENT EVALUATION 1

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STANCPIPE FEEDWATER LINE

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.* PROGRAM DIRECTION e PROGRAM DIRECTION GRS MPR lH1

  • PROGRAM DIRECTION
  • TECHNICAL e DESIGN SUPPORT e CONSTRUCTION I

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  • UPTF TEST FACILITY
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(MANNHEIM) e UPTF DESIGN i.

CCTF SCTF (TOKAll (TOKAll 1

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I INEL ORNL LASL e FILM PROBES e SPOOL PIECES e TRAC CODE e IMPEDANCE PROBES e DRAG DISKS

  • DESIGN e DATA ACO. SYSTEM e LIO. LEVEL DETECT.
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  • TURBINE METERS
  • POST-TEST g
  • STEAM-vvATER TESTS e DESIGN SUPPORT
  • STEREO LENS g
  • DEVELOPMENT (INSTR.)
  • AIR-WATER TESTS e MODEL TESTS DD N

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