ML20207A192
| ML20207A192 | |
| Person / Time | |
|---|---|
| Issue date: | 11/22/1985 |
| From: | Bassett O NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Goldman D ENERGY, DEPT. OF |
| Shared Package | |
| ML20207A169 | List:
|
| References | |
| CON-FIN-A-2016-6, CON-FIN-A-2026-6, CON-FIN-A-2220-6, CON-FIN-A-2232-6, CON-FIN-A-2255-6, CON-FIN-A-2257-6, CON-FIN-A-2260-6, FOIA-86-678 NUDOCS 8611070253 | |
| Download: ML20207A192 (8) | |
Text
i NI M -678 NOV2 212 6 !
I Hr. David T. Goldman, Area Manager l Argonne Area 3ffice l U. S. Departmelt of Energy 9800 South Cas ; Avenue Argonne, Illir ais 60439
Dear Mr. Geldman:
FY 1986 NUCLEAR REGULATORY RESEARCH ORDER NO. 60-86-001 FOR ARGONNE NATIONAL LABORATORY Please authorize Argonne National Laboratory to execute the program described in the enclosed NRC Order.
If this meets with your approval, it is requested that acceptance be indicated on the enclossd form and the original be sent to the NRC Office of Resource hanagement and one copy returned to this office.
Sincerely, t
- 0. E. Bassett, Director Division of Accident Evaluation Office of Nuclear Regulatory Research Enclcsures: Distribution:
- 1. fiRC Order Subj
- 2. Program Briefs Circ Chron cc w/ enclosures:
R. W. Barber, DOE /EP 9lu e, ORM (1 Ishii, ANL R. Lee, DAE (A2026)
L A $1 k, ANL L. Chan, DAE (A2016, A2232)
I ns ANL n. E 2 5 V. L. Shah, ANL P. Wood, DAE (A2257)
W. T. Sha, AHL 5.TAE(A2260)
. Hos ans, DAE
- 8. W. Spencer, ANL Wylbur
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- u s. NUCLEAR REoutATORY cOuulssCN ORDER NUMBER NRC FORu 173 ,
"3 60 001 l
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STANDARD ORDER FOR DOE WORK NOV 2 21985 l'SSUED TO: (DOE Offee) ISSUED SY: (NRC Offce) ACCOUNTING C'TATION APPROPRIATION SYMBOL Division of Accident 31X0200.605 Argonnej Area Office Evaluation ,,, ,vo,,,
PERFoRusNG ORGANIZATION ANO LOCATlON See Attached FIN NUuSER Argonne National Laboratory See Attached WORIC PERIOO - TNIS ORDER F#4 TITLE FIXED O ESTIMATED E See Attached FRou. TO:
10/1/85 9/30/86 OstlGATION AVAILABILITY PROVIDED BY:
A THIS ORDER : 1.555.000 0 TOTAL OF ORDERS PLACED PROR TO THis DATE WITH THE PERFORMING ORGANIZATION UNDER THE
- SAME *APPROPRIATON SYMBOL" AND THE FIRST FOUR DIGITS OF THE "B&R NUMBER ~ CITED ABOVE 533,000 C TOTAL ORDERS TO DATE (TOTAL A & B} $
g gggggg D AMOUNT INCLUDED IN "C" APPLICABLE TO THE " FIN NUVBER" CITED IN THIS ORDER $
See Attached FINANCIAL FLEXIBILITY C FUNDS WILL NOT BE REPROGRAMMED BETWEEN FINS LINE D CONSTITUTES A UMITATCN ON OBLIGATIONS AUTHORIZED 2 FUNDS MAY BE REPROGRAMMED NOT TO EXCEED r10% OF FIN LEVEL UP TO 550K UNE C CONSTITUTES A LIMITATION ON OBUGATONS AUTHORi?ED STANDARD TERMS AND CONDITCNS (see NRC Manuai Chapter 1102. Appendis Part a) ARE PART OF THIS ORDER UNLESS OTHERWISE NOTED ATT ACHMENT S THE FOLLOWING ATTACHMENTS ARE HEREBY MADE A PART OF THIS SECURITY.
ORDER C WORK ON THIS ORDER INVOLVES CLASSIFIED 2 $TATEMENT OF WOAK INFORMATION NRC FORM 187 IS ATTACHED O ADDITONAL TERMS AND CONCiTONS C WNK ON THIS ORDER INVOLVES UNCLASSIFIED SAFEGUARDS, PROPRIETARY, OR OTHER SENSITIVE C OTHER INFORMATON F RE BLE K U WORM ON THIS ORDER IS UNCLASSlFIED AND NOT SENSITIVE REMARKS tRererence the proposa! 01 number and care oms m0* core of the attached statement of wors modutes the DOE proposag The contractor will follow general guidelines which have been provided in U.S.
Nuclear Regulatory Commission Manual Chapter NRC-1102, " Procedures for Placement of Work with the Department of Energy." The reports to be generated shall not contain any proprietary, confidential or copyrighted material without written pennission from the institutions and organizations to which the infonnation may belong.
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@(g d ISSUING At$f)4 MITY ACCEPTING ORGANIZATION ScNAheSLA ew aAu
- 0. E. Bassett, Director ScNATuRE
- trTLE Division of Accident Evaluation Trite Office of Nuclear Regulatory Research ATE NRC rORu m t,p I
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e .w-s SOEW #60-86-001-ARGONNE NATIONAL LABORATORY.
. FY 1986 -
(DOLLARS IN THOUSANDS)
FY 86 - -
BAR NO. FIN NO. TITLE OBLIG 601920 A2026-6 Phenomenological Modeling of Two-Phase Flow in Water Reactor $' 240:
Safety Research _ ,
601930. 'A2016-6 Transient Fuel Response and Fission Product Release 250 601930 .A2220-6 Examination'of TMI-2 Fuel Specimens 300 601930 A2232-6 Post-Test Exam (ORNL Fission Product Release Test Specimens) 150 601930 A2255-6 COMMIX Calculations 100 601930 A2257-6 Ice Condenser MSLB Analysis Methods 150 601930 A2260-6 Corium-Coolant Mixing 365 TOTAL $1,555 4
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I N FORW307 u.s. NUCLEAR REGULATORY Commission t si%nuwses
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DOE SOURCE SELECTION JUSTlFICATION A2260 2 FsN r TLE 3 SELECTED 50umCE Corium-Coolant Mixing Argonne National Laboratory
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ANL has a unique combination of experimental facilities and expeAt scientists with extensive knowledge of corium-coolant mixing phenomena and the existing computer codes and models. ANL has an expensive test vessel, the COREXIT Test Vessel, which was paid for by EPRI and which is available for NRC work. This test vessel will be used at no capital cost to the experi-mental program. Thus, the use of the ANL facilities is cost effective. ANL has well qualified scientists who can satisfy NRC contract work requirements because of unique technic < l backgrounds based on several years of corium-coolant mixing experiments for EPRI and others.
In addition, ANL scientists have extensive experience in analyzing several sets of corium-coolant mixing experimental data over the last five years. ANL scientists are knowledgeable of avisting corium-coolant mixing models and have extensively published their research resus ts of model-experiment comparisons. This combination of technical experience both in experiments and analysis gives ANL the required set of disciplines for this NRC contract work. For evaluation of phenomenological computer codes ANL has no vested interests and therefore can meet the NRC requirement fo complete objectivity for this contract work. The above reasons make ANL the best qualified for this project.
Note: Project funds for A2260 were split from A1030. The funding for both projects, A2260 and A1030, does not exceed previous funding for A1030.
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4 October 1,1985 FY 1986 Program Brief Program: DAE
Title:
-Corium-Coolant Mixing Fin No.: A2260 Contractor: Argonne.
Site: Chicago State: Illinois NRC Technical Monitor: Task A - J. L. Telford Task B - J. L. Telford and J. Hopenfeld Principal Investigator: Task A - B. W. Spencer Task B - R. P. Anderson Objective: To perform designed experiments and analyses for-the phenomena governing corium-coolant mixing.
Budget Activity: 601930 FY 1986 PROGRAM: TASK A - $ 205K' TASK B - $ 160K TOTAL 5 365K FY 1986 Scope:
(10/1/85 - 11/30/86) l Task A - B. W. Spencer l 1. Conduct a set of designed experiments in the COREXIT Facility to f investigate the effects of two independent variables on corium breakup, mixing, quench rate, hydrogen generation, and debris characteristics.
A. The independent variables are: water depth and number of holes in a submergered stainless steel plate.
(1) The two levels of water depth are: " low" is 23.8 inches (60.5cm);"high"is42 inches (106cm). The water depth is measured from the bottom of the water chamber to the top of the steel plate with about 0.25 inches of water above the steel r plate.
(2) The two levels for number of holes in a submerged stainless steel plate are: " low" is four (4) holes arranged in a
" triangular" array 0.8 inches (2 cm in diameter, spaced 3 cm '
center to center; "high" is seven (7 holes arranged in a
" triangular" array,0.8 inches (2cm in diameter spaced 3 cm center to center. These holes are in two different stainless steel plates each of which will represent a submerged lower grid forging (13.5 inches thick) in their respective tests.
B. The fixed experimental conditions are: {
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?! Fin No.: A2260 2 October 1,1985 (1) Delivered melt temperature is about 2800*C.
(2) - The cover gas is argon.
(3) A nonzero subcooled water temperature, to be determined during pretest analysis.
(4) System pressure is one atmosphere.
(5) Melt entry velocity is about 4 m/s.
(6) Delivered corium melt' mass is 10 kg.
C. The experimental matrix is g'iven below.
Corium-Coolant Mixing Series Water Number Test Depth (cm) of Holes 1 60.5 4 2 106 4 3 60.5 7 4 106 7 D. The measurements made before, during, or after each test include:
water and cover gas pressure and temperature, conversion ratio (in the event of an explosien), physical debris characteristics, chemical debris characteristics (including e.g., XRD, SEM, oxidation states),
hydrogen generation, quench rates, X-ray motion pictures, optical motion pictures in the pipeway exiting into the expansion vessel, and amount of breakup and mixing.
- 2. Analyze the experimental conditions er approach of item 1, given above, for possible improvements; provide the written analysis to the NRC Technical Monitor before start of tests. All changes to the specified experimental conditions must be approved by the NRC Technical Monitor.
- 3. Provide technical consultation on specific topics related to corium-coolant mixing and make presentations, as requested by the NRC Technical Monitor.
- 4. Approximately four progress review meetings will be held during FY 1986.
- 5. Provide quick-look data reports to the NRC Technical Monitor on a timely basis following completion of each test.
- 6. ProEidemonthlyprogressandcostletterreportsitemizingbysubtask activity and any travel. Summarize project activities for the past month and identify any problems that might affect project milestones. This report will be submitted to the NRC Technical Monitor by the 10th of each month.
1 Fin No.: A2260 3 October 1, 1985
- 7. Provide a final report by November 30, 1986 including results from all four tests, interpretation, and model comparisons.
Task B - R. P. Anderson
- 1. Conduct a set of designed experiments for the Statified Contact Mode to '
investigate the effects of three independent variables on gas phase pressure, liquid phase pressure, depth of mixing, and energy conversion ratio. The independent variables are: surface area of interaction, separation space, and temperature difference. Photography of the experiments will be used extensively. The materials used will be freon and water or other materials (e.g., salt or tin) as approved by the NRC Technical Monitors.
- a. The text matrix, experimental conditions, and schedule will be jointly determined by the Principal Investigator and the NRC Technical Monitors (with advice from consultants).
- b. This series of experiments will be conducted first.
- 2. Conduct a set of designed experiments for the Pour Contact Mode to investigate the effects of four independent variables on gas phase pressure, liquid phase pressure, and energy conversion ratio. The independent variables are: liquid slug height, mass ratio, compressible volume, and temperature. Photography of the experiments will be used extensively. The materials used will be freon and water or other materials (e.g., smelt and water) as approved by the NRC Technical Monitors,
- a. The test matrix, experimental conditions, and schedules will be jointly determined by the' Principal Investigator and the NRC Technical Monitors.
- b. This series of experiments will be conducted second.
- 3. Provide technical consultation on specific topics related to corium-coolant mixing and make presentations, as requested by the NRC Technical Monitors.
- 4. Approximately four progress review meetings will be held during FY 1986.
- 5. Provide quick-look data reports to the NRC Technical Monitors on a timely basis following completion of each experimental series.
- 6. Provide monthly progress and cost letter reports itemizing by subtask activity and any travel. Sumarize project activities for the past month and identify any problems that might affect project milestones. This report will be submitted to the NRC Technical Monitors by the 10th of each month.
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~
1 Fin No.:~ A2260 4 October 1,1985 1
- 7. Provide'a final report by September 30, 1986 including results from .111 tests, interpretation, and any model comparisons.
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