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Forwards Preliminary Descriptions of melt/retention-matl & Melt/Concrete Tests Conducted by Sandia Lab in FY79. Viewgraphs from Sandia mid-year Presentation Encl
	ML19276F377
Person / Time
Issue date:	03/14/1979
From:	Sherry R; NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Walker D; OFFSHORE POWER SYSTEMS (SUBS. OF WESTINGHOUSE ELECTRI
References
	NUDOCS 7903290072
	Download: ML19276F377 (88)
	v • d • e

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UNITED STATES

[.g

.t NUCLEAR REGULATORY COMMisslON 3 k.i

)

WASHINGTON, D. C. 20555

^k/j' e.....-

.ua 14 m; Dr. Dee H. Walker, Manager Nuclear Safety and Licensing Offshore Power Systems 8000 Arlington Expressway Box 8000 Jacksonville, Florida 32211

Dear Dr. Walker:

Per our earlier telephone conversation I am sending the preliminary test descriptions for the melt / concrete and melt / retention-material interactions tests which have been, or will be conducted during FY 1979 at Sandia Laboratory.

Included in the list are tests which are funded by Advanced Reactor Safety Research (ARSR) in additicn to the tests funded by the Fuel Behavior Research Branch (FBRB).

I am enclosing copies of the viewgraphs used by Dana Powers, et.al.,

during the Sandia Mid-Year Review presentations. Also attached is a brief synopsis of Gennan research programs in the LWR core melt area.

This material was summarized from the July,1977 Commission of the European Communities compilation of comunity nuclear safety research projects.

Sincerely,

... R. Sherry Fuel Behavior Research Branch Division of Reactor Safety Research cc w/o encl:

T. Spies, ARB cc w/ encl:

A. Marchese, ARB M. Berman, Sandia R. Birkel, DPM C. Haupt, DSE G. Chipman, DSE (2).

7903290012_

6rrJosueC.

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SANDIA MOLTEN CORE /,QOflCRETE INTERACTIONS PROGRAM BREAKDOWN RSR RESPONSIBILITY SANDIA TASK FBRB FIN # (A1019)

ARSR FIN # (Al218)

Large Scale Sustained Tests I

Coil Series Coil 9L All execpt coil 9L Development of Large Furnace All l

Core Retention Materials Tests All Small Scale Sustained Tests Core Retention Materials (CATil Series)I All I

Burn Series All I

F Series All Small Scale Transient I

All XR Series flodel Development CORCON Development and Testing All All Concrete Modeling lleat Transfer tiodel Development, Simulant, and Separate Effects Tests All Instrumentation Development Part Part Description of Test Programs Attached

SMALL SCALE MOLTEN CORE RETENTION MATERIAL INTERACTIONS TESTS CATH SERIES TESTS Test (Sponsor)

Crucible / Melt Technique Approx. Date Objective /Resul ts CATH-1 Mg0 Brick Transient Completed Reported in (ARSR)

Termite Generated CATH-2 MgG Brick Transient Completed Reoorted in (ARSR)

Thennite Generated CATH-3 Mg0/ Steel-Iron Oxide Inductive Heat-May 1979 Observe rate of slag-line (ARSR) ing attack on M40 to confinn model advanced for this attack.

CATH-4 fig 0/ Steel Inductive June 1979 Melt flow in flaws and cracks in t10 bricks.

(ARSR)

Heating 9

CATH-5 Borax /Corium Inductive June 1979 Debris erosion and dissolu-(ARSR)

Heatina tion by Borax.

"I As in CATH-3. This test CATH-6 Mg0/Cori tsn Inductive

?

(ARSR)

Heating will mimic a similar test to be done in-pile.

CATH-7 High-Alumina Cement /

Inductive June 1979 As in CATH-3 (ARSR)

Co rium tiea ting a) Test design awaits specifications for the in-pile tests

LARGE-SCALE CORE RETENTION TESTS Test (Sponsor)

Crucible / Melt Technique Aporox Date Objective /Resul ts HAC-1 liigh Alumina Cement Melt teemed at 1700 C Completed Emsion Rates of liigh (ARSR) 200kg ss Sustained by Induction Altsnina Cement Heating flAC-2 liigh Alumina Cement fielt teemed at 1700 C July 1979 Erosion Rates of High (ARSR) 200kg ss Sustained by Induction Alumina Cement Hea ting

?

Borax /200kg ss Transient fnitial Temper-Completed Holten Steel Eroded (ARSR) ature 1700 C Borax by Melting.

Maximum penetration of 7 cm at CL of crucible.

?

Mg0/122kg ss Melt teemed at 1700 C Completed Inductive coupling (ARSR)

Sustained by Induction was inadequate for a flea ting satisfactory test.

Limited Slag-line attack observed.

?

Firebrick Lined base /

Helt teemed at 1700 C Completed Very little gas (ARSR) 213kg ss Sustained by Induction evolution.

Firebrick Heating penetration rate annroximately 8.5(10)-4 cm/sec.

?

Future Tests

SMALL-SCALE MELT / CONCRETE INTERACTIONS TESTS X-RAY SERIES Test (Sponsor)

Crucible /Mel t Technique Apnrox. Date Objective X-RAY 1(a)

Concrete / Steel-Al 0 Thermitically generated April,1979 Directly observe 23

~

(ARSR) mel t.

X-ray scanning in behavior of high-real time temperature melt in contact with concrete.

X-RAY 2 Correlate results (ARSR) with data from diag-nostic instrumentation.

X-RAY 3 Provide basis for (ARSR) phenomenological modbls of melt / concrete interactions.

(a)The x-ray test series will involve a variation in melt geometry and concrete composition.

Details of crucible design have not been defined at this date.

m em emp

LARGE-SCALE SUSTAINED TESTS COIL SERIES i

(INCOMPLETE DESCRIPTION) i Test (Sponsor)

Crucible / Melt Technique Approx. Date Objective /Results Coil 1 CRBR concrete /205kg ss Melt teemed at 1700 C Comoleted Inductive heating (ARSR)

Sustained by Induction sustained for 10 min.

lleating maximum erosion (approx.

10cm) occurred a CL of crucible Coil 9L CRBR Concrete /200kg ss Melt teemed at 1700 C July,1979 To be used as standard (FRBR)

Sustained by Induction problem for CORCON/

Heating HECHSL comparison

?

Future Tests

SMALL-SCALE MELT / CONCRETE INTERACTIONS TESTS f SERIES Test (Sponsor)

Crucible /Mel t Technique Approx. Date Objective Inductively (a) Heated August 1979 Influence of mel t F-1 CRBR Concrete /25kg Steel size and internal (FB) heat generation on mel t/ concrete inter-action.

F-2 CRBR Concrete /25kg Steel (FB)

(a) Techniques similar to those used in tests 5 and 6.

SMALL-SCALE MELT / CONCRETE TESTS BURN SERIES Test (Sponsor)

Crucible /Mel t Technique Approx. Date OBJECTIVE / REMARKS BURN 0 Limestone Concrete / Curium Sustain a the'mitically Comple ted Wild variation in (FB) generated corium melt at resistivity of oxide temperature using Joule phase made control Heating supplied via two of the DC power supply tungsten electrodes buried di f ficul t.

After in concrete. Also observe approx. 30 secs. over-interactinn between corium loads occurred and mel t and candidate refractories the test was terminited.

- W B, HfC, Y 0, Zr02 (Ca0) 2 2

BURN 1 Limestone Concrete Utilize x-ray imaging tech. Completed Test BURI 1 was quite (FB) to observe melt / concrete success ful. Brief interface in real-time results and collateral data reported in reference 1.

BURN 2 Limestone Concrete / Steel Utilize inductive heating Comple ted Test BURN 2 was quite (FB) to warm steel up to near success ful.

Da ta its melting point while in have been reported in contact with concrete.

Test reference 1.

E rosion simulated both the inter-of concrete began at action of fragment debris approx,13000C - a beds with concrete and the temperature below interaction of core mel ts liquidus. of concrett late in an accident when but well above solidus.

melt solidification occurs Downward erosion and the concrete has been approx. 3 cm/hr. Radial largely dehydrated erosion approx.1.7cm/hr

SMALL-SCALE f1ELT/ CONCRETE TESTS BURf4 SERIES (00 tit.)

Tes t (Sponsor)

Crucible /Mel t Technique Approx, Date Objective /Rema rks BURN 3 Generic Southeastern Similar to test BURti 2 with Completed Result analogous to (FB)

United States Concrete a more refractory concrete those of test BURN 2 and with more extensive reported above ins trumentation BURN 4 Generic Southeastern Deposit a thermitically Completed Prompt gas release at (FB)

United States Concrete generated mel t into concrete the time of melt inpact and sustain that melt by on the concrete caused inductively heating metallic the melt to be expelled phase from crucible cavity.

Instrumentation from crucible were destroyed and the test was terminated BURN 5 Basaltic Concrete /5kg Inductively (a) heat from flarch 1979 Observe behavior of (FB)

Steel cold start hot, but unmolten cg debris on concrete BURN 6 CRBR Concrete /Skg (FB)

S teel BURN 7 Concrete /7kg Corium (FB)

BURN 8 Concrete /7kg Corium Inductively heat and May 1979 Develop technique for (FB)

Joule heating supplying power to oxide as well as metallic phases of core debris

Techniques used in BURN test series to be found in SAND 78-1901 (b)Particular attention is to be paid to gas generation and the directional nature of concrete erosion.

FB = Fuel Behavior Research Branch U.S. Nuclear Regulatory Conmission Ref.1 - g igWater Reactor Safety Research Program Quarterly Report, April-June,1978 in publication,

rcio.u w a VISUAL AIDS USED IN STATUS CF ':ELT/CONCFETE INTERACTIONS STUDY Ey D. A.

Fcwers Sandia Laboratories Division 5831 Albuquerque, New Mexico 87185 Presented at the midyear program review Feb., 1979 Silver Springs, MD The Molten Core / Concrete Interactions Study was prompted by results of the Core Meltdown Experimental Review.

This ra'riew inficated that fuel /ccolant interactions and melt / concrete interactions were areas of great uncertainty in postulated scenarios for hypothetical core meltdown accidents in nuclear reactors.

The experimental study of these melt / concrete interactions on behalf of the Fuel Behavicr Branch is now about to be concluded.

It is appropriate, L en, that the current level of understanding of these interactions and the remaining areas of uncertainty be summarized.

At its inception the e::perimental program was to be a qualitative, engineering scoping study to identify those phencmena and processes pertinent to questions of nuclear reactor safety.

The experimental effort was to use prototypic materials and con-ditions.

The goal was to provide data that would either confirm or refute assumptions made in previous, analytic investigations of the melt / concrete interactions during core meltdown accidents.

Pecults of these qualitative examinaticns are compared in the enclosed table to assurptions made in WASE-1400(2) con-cerning the melt / concrete interactions.

The more important of these differences are listed on Slide 1.

At the conclusien of the qualitative work the prcgram was expanded in conjunction with Advanced Reactor Safety Branch to quantify some of the phenomena that seemed to have the most severe impact en the postulated accident scenario.

The goal of this aspect of the work was to construct a model of the melt /

concrete interaction process that would be suitable for the purposes of:

a) sensitivity analysis b) risk assessment The concern in meltdown accidents is with cantainment failure.

Reacter containment may be failed by the erosien of the concrete sump of the reacter (Slide 2).

A more severe threat to containment integrity is posed by the gases generated during melt attack on the concrete.

These gases may fail containment by everpressurizing it, or they may detonate and fail containment.

Regardless of whether either of these drastic events occur, the gases produced during melt / concrete interactions have a major impact on the interaction process.

If one were to name a single result of the qualitative study that disagreed most with previous assumptions concerning the melt / concrete interactions it would be gas behavior.

If one were to name a single process that had the mest impact on quantitative aspcets of the melt / concrete inter-action it would again be the generation and escape of gases.

Gases are formed by the thermal decomposition of mencrete.

Considerable understanding and a computer model of this de-composition process have been formulated in this research (Slides 2 and 3).

Separate effects tests have shown that the rate at which concrete is eroded is related to applied heat flux lincarly within the errors of the experimental data (Slide 4).

How the heat flux passes from the melt to the concrete is however an area cf uncertainty (Slides 5 and 6).

Several mcdels have been suggested for this heat transfer process.

None of these models is entirely satisfactcry and none is experimentally confirmed.

During this work an x-ray te:hnique has been developed that allows direct observation of a high temperature melt in contact with concrete.

This technique premises to relieve some of the uncertainty if it can te allied with quantitative, heat flux sensors.

Until this is acccmplished the technique does yield substantial information concerning the melt / concrete interactions.

Cata produced using the x-ray technique indicate that gases are released into the melt neither randemly, nor uniformly.

Rather, localized sites develop cn either side of the centerline of the crucible, and along the walls of the pocl.

Release along the walls tends tc shield these walls from attack by the melt (Slide ().

This effect may be clearly seen when post-test erosion profiles of basaltic (low gas release) and limestone (high gas release) crucibles are compared (Slide 7).

As gases pass through the melt they are chemically reduced (Slide 13).

The oxygen fugacity of the gases is buffered by the FeO/Fe equilibrium (Slide 14).

Since the C & H ccntents of the 2

gas stream are known and since the oxygen concentration is buffered, the evolution of gas composition with temperature may be estimated (Slide 15).

Such estimations suggest that methane formation may occur in reactor containment if the reduced gases are not ignited.

Extensive methane ferr.ation has been observed in ene of our experiments (Slide 16).

Methane formation will reduce pressurization within in con-tainment but it may also increase the hazard of detonation within containment.

Methane formation from CO and H is known to be a kinetically 2

rather than thermodynamically controlled reaction.

Some ex-perimental data indicate that catalysis of this reaction is pcssible.

Eut this possibility is still an area of uncertainty (Slide 17).

We have agreed to a code comparison with Projekt Nukleare Sicherheit of KfK.

Ccmparison will be based on two standard tests (Slide 13).

Not all the data generated in these tests vill be strictly for code comparisen.

Some will be used to improve the codes which are not now equipped to provide quantitative estimates of these data (Slide 19).

This code comparisen will be a useful exercise and will certainly provide scme information concerning the severity cf the areas of uncertainty listed abcVe.

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GERMAN (MELTDOWN) RESEARCH PROGRAMS
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Task Task #
Lab Investigators Conments Decay Heat Measure-PNS 4234 KfK/RNS K. Baumung Completed 1978 ments U235 (10-1000 sec)
Exp. Investigation PNS 4321/
KfK/PNS Dr. S. Hagen Co*nleted 1978.
Investigate Exp.
of Meltdown Phase of 4241 Meltdown & Resolidification of UO2-Zircaloy fuel Fuel Rod. Temperature >20000C Under ECCS Conditions Reached Partial ECCS Failure to be Considered.
Verification of Ro
__RS 205.
. Univ. of.Stuttgart Prof. H. Uncer/
Completed 11/30/78. Funds 347KDM.
s Experiments & Fuse Institute of Nuclear Dr. F. Schmidt Goal: Development of Model for
, Protection by MELSIM Eseroy & Power Meltdown Process and Verification of EX-MEL Sys tems PNS 4240. Expts - To be included in MELSIM Model (Primarily in Module ABSINK.
Investigation of the RS 211 Univ. of Stuttgart... Prof. H. Unger/
Completed 3/31/78. Funds 178KDM.
Phase 'Between Core Institute of Nuclear
.D. P. Koerber
~~Purpose:~~
Modeling of Fuel Melt-Failure and Accumu-Energy and Power down Following Grid Plate Failure lation of Molten Systems Until Fonnation of a Molten Pool Materials: Integra-(in the Lower RPV) & Evaporation tion of MELSIM 1 of Residual Water into BILANZ for Cal-(Modeled in Program LUECKE) culating the Energy to be Combined with MELSf &
Balances Following BILANZ.
d RPV Failure Technology and RS 200/
KfK/PNS Dr. S. Nazare/
funds 1 102KDM. To Determine Properties of Coritsn PNS 4245 IMF I Dr. G. Ondrance Properties of Cortum
GERMAN (MELTDOWN) RESEARCH PROGRAMS - 2 Task Task #
Lab Investigators Comments Theoretical and RS 166 T. U. Hannover Prof. F. Mayinger 1,372KDM.
Cempleted 12/31/78.
Experimental Inves-
~~Purpose:~~
Model the Themal Inter-tigation of the action of Molten Core with Reactor Themal-hydraul ic Components.
Primarily Studies of Behavior of a Molten Heat Transfer Between Melts and Core in the Reactor Concrete and Design of Melt Collec-Vessel and with tion Equipment. Parametric Studies Concrete Utilizing the BETON Multilayer Melt Heat Transfer Program.
Measurements of the RS 214 Battelle/ Frankfurt R. Skoutajan 369KDM.
Completed 11/30/77. Measure High Temperature the Viscosity of 0xidic Core Melts Visosity of Selected (and Modures of Corium & Concrete)
Wmvf0 Substances which are of Significance for Core-Melt Accidents Best Estimate Calcu-RS 311 GRS Dr. J. Keusenhol f To be Completed 3/31/79. 673KDM.
To Examine the Range of ECCS Failures.
lations for the to determine the Threshold Between Expanded Study Pro-Ul timate Coolability and Partial gram of the Core-Meltdown.
Meltdown Project Emergency Core RS 310 Babcock - Brown Dr. G. Houry 7SlKDM. Completed 12/31/78.
To Cooling Analysis Baueri Detemine the Conditions for: the
"* " ' ' the Framework Onset of Core Melting (Identical of the Core Mel t-Project to GRS RS 311 ).
ing Research Project
GERMAN (MELTDOWN) RESEARCH PROGRAMS - 3 Task Task #
Lab Investigators Comments Experimental Study RS 76A Euratom - JRC Ispra H. KoHowski/
200KDM.
Completed 12/31/78.
To of Steam Explosions H. Hohmann Study Themal Interaction Between Water and Molten Steel, Holten UO2 and 002 Granulates.
Detemine Pressure Buildup and Themal to Mechanical Energy Conversion Efficiency -
(Shock Tube Experiments & Tank Tests)
Develop KAMI-WA Computer Code.
Shock Tube: Melt Quantity - < 150g System Pressure T 1 to 25 Tank Test:
Mel t Quantity - < 4khar System Pressure - ?
Theoretical Simulation RS 206 Univ of Stuttgart Prof. H. Unger/
558KDM. To be Completed 6/30/79.
of Steam Explosions in Dr. R. Benz To Estimate upper Energy Release Pool-type Geometry and Pressure Buildup from Steam Development of Models Explosion and Development of Com-Describing the Frag-puter Models for the Fragmentation mentation Process; Process. Verify Euratom JRC Ispra Experimental Research Experiments.
on Highly Transient Boiling Investigation of the RS 154 KWU/Erlangen Dr. M.' Peet.;
Completed 12/31/77. 1,692KDM.
Interaction Among Core Interactions (multi-kilogram) Corium and Steel Melts with Concrete have Melts and Concrete been Completed.
Concrete Themal Conductivity and Themal Capacity Tests have been Completed.
GERMAN (MELTDOWN) RESEARCH PROGRAMS - 4 Task Task #
Lab Investigators Conments Composition and PNS 4314 KfK/PNS H. Holleck/
To Investigate the Chemical Inter-Reaction Behavior of (4244)
A. Skokan actions Between Core Melts, Fission Products and Concrete Including LWR Materials in Core Melt Tests and vaporization Tests.
Helting Conditions To Detemine the Partitioning of Fission Products Within the Melt (i.e., Metalic vs. Oxidic Layers).
Engineering Study on RS 237 KWU/Erlangen R. Goetzmann/
Completed 10/31/77. Funds 11KDM.
H2 Fomation During (Joint Study with H. Hassman To Determine Whether the Decom-the Interaction of KfK) position gases (H2 ) from Melt /
0 Concrete Interaction Which are Core Mel ts wi th Reduced during Passage Thru the Concrete Melt to H2 will Pose a Threat to Containment Integrity.
ZUEND Code Developed (Calculates Combustion Processes Within Containment) and Incorporated into the COC0 Contain-ment Code.
Steam Generation RS 288 KWU/Erlangen C. Goetzmann Completed 2/31/78. Funds 215KlH.
To Calculate the Heat Balance After Core Melt (Strong Project Flooding Relationship with following RPV Failure.
Results to T. U. Hannover) be Integrated into BILANZ. To Detennine the Amount of Heat Removed from the Melt When Cooled from the Top by Sump Water. What Effect does Steam Generation have on Containment Pressure. -
GERMAN (MELTOOWN) RESEARCH PROGRAMS - 4 Task Task #
Lab Investigators Comments Experiments with PNS-4323 KfK/PNS D. Perinic To Define Quatitatively the Inter-Simulated Large (4246) actions of Melts with Concrete, Core Melts Sand, etc. (Fourth Phase) and to Verify Appropriate Computer Codes.
To Study Long Term Behavior of Melts.
To Characterize Gas and Aerosol Release from Melts During Interaction with Concrete.
Develop Melt System for Studying Simulated Melts in the ExapndSAS(llA 100-1000kg range.
test System from 0.5 to Sgm Capacb ty for Inductively Heated Corium Melts.
Develop Induction Heating Capability of Steel 0xide Melts with 300kg Capabil ity. Thermitically generated Melts (300kg max) have been Generated within Concrete Crucibles.
Energy Balance follow-RS 183 KWU/Erlangen H. Goetsmann Complete 3/31/78.
Funding 400KDM ing RPV Failure with H. Hassmann (Incomplete Description)
Allowance for Concrete Disintegration Theoratical Analysis RS 293 Battelle/ Frankfurt Dr. W. Baukal Complete 10/31/78.
Funds 222 KIN.
of the Effects of Heat To Determine the Enthalpy Change for in Core Melt / Concrete each Individual Reaction which Occurs Interactions During Core / Concrete Interaction &
to Determine the Oxidation - Reduc-tion Behavior in the Melt.
GERMAN (MELTDOWN) RESEARCH PROGRAMS - 5 Task Task #
Lab Investigators Comments Interaction Between RS 296 KWU/Erlangen Dr. M. Peehs To Be Completed 9/30/79. 675KDM.
Core Melt and the Tn Determine the Interaction of Core Extended Pedestal Melt / Concrete Decomposition Products Zone with the Rock and Soil Below the Concrete Basemat.
Experiments on PNS-4315 KfK Dr. H. Albrecht
Complete 1978. To Study the Release Determination and (4243) and Transport of Radioactive materials Limitations of under Various Core Mel tdown Condi-Fission and Acti-tions; the Study of the Physiochemical vation Product Forms of the Released Radioactive Releasi During Core Matc.ials. Experimental Program:
Mel tdown g
30g Samples of Inactive Corium Inductively Heated.
o ' 309 Corium Made with Activated Structural Materials '.Zirc, Steel).
o - 309-3kg Corium with Low Level Fission with Simulated B.U. Between 10,000-50,000 MWD /T.
o Release From Corium-Fia;i' n-Con-o crete FM1ts Tests Conducted in SASCHA Induction Mel t Furnace.
Release into Steam and Inert Atmospheres Development and
__,PNS-4 316 KfK Dr. Perinic To Study the Release and Transport Operation of Systems (4243)-
of Radioactive Materials Under for the Study of Various Core-Mel tdown Conditions.
Fission Product Develop Equipment for Conducting Release During LWR the Tests Described under PNS 4315.
Core Meltdown
GERMAN (MELTDOWN) RESEARD1 PROGRAMS - 6 Task Task #
Lab Inves tiga tors Comments Interaction Between PNS 4311 KfK Dr. W. Schoeck To Model the Natural and Artificially Fission Products and Aerosols in LWR Induced Deposition of Aerosols in Containments the Containment Following Severe LWR Accidents.
Develop and Verify Experimentally a LWR : Containment Aerosol Removal Code (NAUA). Testing will Include Soluable as Well as U02 Ae roso's.
O
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CORCON - PRIfCIPAL FEATURES I GEOMETRY D, AXISYMMETRIC MULTILAYERED POOL - 1 TO 4 LAYERS
- ISOTHERMAL CORE MELT ATMOSPHERE
- ISOTHERMAL, REACTItJG GAS MIXTURE I
SURROUNDINGS VENT MELT ATMOSPHERE T0 CONTAINMENT
( REACTING GAS MIXTURE )
I 1
COOLANT /
d COOLANT LAYER l
CONCRETE
/
OXIDIC LAYER INTERFACE j
REGION I
METALLIC LAYER CONCRETE i
F i
OXIDIC LAYER (PRINCIPALLY UO }
2 f
f N.
MELTICONCRETE CONCRETE INTERFACE REGION
COX ON - PRINCIPAL FEATURES 11 INSTANTANEOUS DEPOSITION OF MELT INTO CAVITY MELT / CONCRETE INTERFACE -
{
VARIABLE AROUflD
- FLOW CONFIGURATION
- HEAT AND MASS TRANSFER
}
POOL
~
MASS A!jD ENERGY CONSERVAT10f1 -
- TRANSPORT - MELT / CONCRETE INTERFACE
- BETWEEN POOL LAYERS
- FROM POOL SURFACE - ATMOSPHERE
- SURROUf1 DINGS
- ATMOSPHERE TO SURROUNDINGS
- VENTING TO C0fjTAINMENT
- SOURCES /
- CONCRETE DECOMPOSITION SINKS
- CHEF 11 CAL REATIONS
- FISS10f! PRODUCT DECAY HEAT
- ASLATION OF SURROUt!Dl!JGS CONCRETE EROSION D, STEADY-STATE ABLATION D, AXISYMMETRIC CAVITY
- CONCRETE DECOMPOSIT10f! DATA CHEMICAL REACTIONS - OX1DAT10fl - METALLIC LAYER
- REDUCTION - OXIDIC LAYER
- EQUILlBRIUM - GAS PHASE IMPROVED MATERIAL PROPERTY DATA POOL VOID FRACTION AND LEVEL SWELL IMPROVED flUMERICAL TECHij10UES
MASS AtJD ENERGY TRANS10RT, SOURCES SURROUNDINGS I
1 ATMOSPHERE I
M+E
=- CONTAIN-1 MENT i
I 3
ER f
3
'E "M+E "E M + E M+E I
i lE E
I 4l COOLANT d
M+E i
I fE
)M+E "E
/
1 A
I i
E E
I I3 OXIDE E
E D
R e
i M+E M+E f,E I
l M+E i
I E
E I
METAL E
E D
R M+E M+E g
==
w E
E n
a M+E E
e g
y W
1 1
E 1 "o
E OXIDE D
M+E M+E I
M+E E
y INTERFACE M+E I
^M+E E
y CONCRETE
CORCON CHEMISTRY I SPEClES:
OXIDIC - 24:
T10, Mn0, Ms0, CAO,
~~S109, 2~~
l CONCRETE NA2, K 0, FE2 3, AL2 3, CR2 3, 0
2 0
0 0
FEO, SRO, BAO, L12, ZR0, NIO, 0
2 U0, pug, PLUS 6 ALUP.INATES 2
2 METALLIC - 5:
FE, CR, Ni, ZR, AND NA GASEOUS C H N 0 SYSTEM:
C, CH, CO, CO, C H, C H, C H26 g
2 22 24 H, H ' H O 2
2 N, NH, N2 3
0, 02 FISSION PRODUCT GROUPS - 4:
METALS:
FPA MON 0X1 DES:
FPa0 FPc0, FPA02 D10XIDES:
2 SESQU10X1 DES:
FPD2 3 0
TOTAL - 49
GECJlfLCHEMISTRY 11 REACTIONS:
MELT / GAS:
OXIDATION - METALLIC LAYER:
REDUCTI0t' - TOP OXIDIC LAYER:
=
CR2 3 + 3H2 0
2CR + 3H O 2
=
CR2 3 + 3C0 0
2CR + 3C02
=
=
FE0 + H2 HO FE +
=
2 FE0 + CD FE +
CO2 N1 +HO NIO + H2 2
NIO + CO N1 + CO2
=
ZR02 + 2H2
=
ZR+ 2H O
=
2 ZR02 + 2C0
=
ZR+ 2C02
=
2FE + ZR02 ZR+ 2FE0
=
FF A + 2H O FPA02 + 2H2
~
2
~
FPA02 + 2C0 FPA + 2CO2
=
GAS PHASE:
THERM 0 CHEMICAL EQUILIBRIUM 0F SPECIF]ED GAS SYSTEM
CORC0f! COMPUTAT10f!S INtilALIZE READ INPUT C ALCULATION DATA COMPUFE INITI AL POOL PROPERTIES AND GEOMETPIES HEAT iR ANSFER WITHIN POOL COEFFICIENTS LAYERS ACROSS POOL I CONCRETE INTERFACE WITHIN ATMOSPHERE INTERFACE INTERF ACE ENERGY POOL I INTERFACE TEMPERATURES BALANCES ADJACENT POOL LAYERS o
POOL / CONCRETE RADIATIVE AND HEAT TRA.NSFER CONVECTIVE POOL / ATMOSPHERE
}
PLUS SURROUNDINGS CONCRETE ASLATION DISPOSITION OF AND SHAPE CH ANGE CONCRETE ABLATION PRODUCTS ERODED CAVITY GEOMETRY CHEMICAL REACTIONS DISPOSITION 0F INVOLVING MELT REACTION PRODUCTS DISPOSITION OF REACTION ENERGIES u
MASS TRANSPORT ALONG INTERFACE ATMOSPHERE-TO -
CONTAINMENT l
o
a i
MELTING OF SURROUNDINGS ADDIT 10N OF COOLANT o
CONSERV ATION MASS AND SPECI ATION OF UPD ATE MASSES OF MASS POOL LAYERS AND ATMOSPHERE MASS TRANSFER ACROSS POOLICONCRETE ENERGY TRANSPORT
~
RELATED INTERFACE BETWEEN ADJACENT POOL LAYERS POOL I A:
PHERE ALONG INTERFACE ATMO5 PHERE -TO-CONTAINMENT MELTING OF SURROUNDINGS ADDITION OF COOLANT o
BETWEEN ADJACENT CONVECTIVE POOL LAYERS POOL / ATMOSPHERE ATMOS PHERE I SUR-ROUNDING 5 o
RADIATIVE POOLISURROUNDINGS v
CHWlC AL E ACD ON ENERGY SOURCES ENERGIES DEC AY HEAT GENER ATION
1 U PD AfE TEMP-CONSERVATION OF POOL LAYERS AND ERATURES ENERGY ATMOS PHERE A
' PHYSI A POOL PROPERTIES
~
OPERTIES t
POOL AND LAYER GEOMETRIES u
ATMOSPHERE GAS PHASE COMPOSITION PROPERTIES EQUltiBRIUM n
,r THERM 0 PHYSIC AL PROPERTIES u
MELTING OF MASS OF MELT SURROUNDINGS PRODUCED u
CHECK PRINT AND PLOT CONTROL RESULTS ?
PAR AMETER S j
TERMINATE COMPUTATION ?
UPDATE TIME u
EQECON PROGRAM MAIN PROGRAM SUSPaVTINES t
DATAIN INITIALIZE CALCULATION INITIAL GEQUll GASPROP GVISCON MLTPROP PROPS COLPROP SDLLIO CONPROP VISRHO CONGE0M POLGE0M INDATPR v
QMLTCON HINTER POOL / CONCRETE HEAT TRANSFER OCOLCON k,iHP00L HRAD 1NTEMP 1
y CONCRETE CONABL CONPROP ASLATION AND CSHPCNG SHAPE CHANGE y
MLTREAC MELT / GAS REACTIONS o
MFLINT GASPROP GEQUIL MASS TRANSPORT ATMLKFL COLFL COLPROP u
MAIN PROGRAM SUBROUTINES
}
ENEP.GY QMDOT GASPROP s,,
TRANSPORT MLTPROP ENTH COLPROP
SURPROP QCONVPL HP00L INTEMP l
QPOLSUR HP00L HATM HRAD INTEMP QATMSUR HATM INTEMP u
FPDHGEN ENERGY SOURCES
}
UPDATE ENRCON TEMPERATURES I
POOL PROPERTIES MLTPROP PROPS SOLL10 COLPROP VISRHO CONGE0M POLGEOM LEV LSWL v
GEQUll ATMOSPHERE PROPERTIES GASPROP GVISCON t
ABLATION OF SURADL SURPROP SURROUNDINGS I
CHECK CONTROL PARAMETERS I
DATAOUT DATFLOT OUTPUT RESULTS
MATERIAL PROPERTIES PROPERTY METALS OXIDES C00LAN' GASES DENSITY
~
PROPS VISRHO D
-GEQ UI L A
VISCOSITY MIXTURE VISRHO T
GVISCON EQUATION A
THERMAL PROPS PROPS F
GVISCON CONDUCTIVITY R
0 SPECIFIC PROPS PROPS M
GEQUll HEAT ENTHALPY ENTH ENTH T
GEQUIL A
SOLIDUS /
PROPS SOLLIO B
L10UIDUS L
TEMPERATURES E
S LATENT IDEAL IDEAL HEAT SOLUTION SOLUTION MODEL MODEL SURFACE DATA FR0M TABLES TENSION
C OM R E T E__Allt. All_0 N /_Sil A P.E_C il AllG E_MO D E L AUCREX/AER0TilERM
- DEVELOP A COUPLED CONCRETE ABLAIl0H AND CAVITY SilAPE CilANGE MODEL ASSilMING: D, AXISYMMETRIC CAV11Y SilAPES
- LOCALLY l-D, STEADY-STATE ABLAT10fl
- UTillZE LATEST AVAILABLE CONCRETE TilERMAL CAPACITY, DECOMPOSifl0H, AND MELTillG DATA
- EVALUATE LIMITATIONS IMPOSED ON APPLICATION OF MODEL BY STEADY-STATE AND l-D ASSUMPTIONS
- PROGRAM INTERFACE AND POOL / INTERFACE IIEAT TRAllSFER COEFFICIEllT MODELS DEVELOPED BY SANDIA
- INVESTIGATE COUPLING BETWEEN llEAT TRANSFER AND SilAPE CilANGE NUMERICS
- IMPLEMENT, CllECK OUT, AND VAllDATE OVERALL CONCRETE IIEAT TRANSFER / ABLATION /
SilAPE CilAllGE CODE O
!-D, STE A DY-STATE CONCRETE ABLATlON
@,+ A )hmix(Tm)
$c.nv
~~kcoa, g~~
-,r---
r------
~'
Q /////////////////
CO NC R ETE k
I I
i________________i q
E h, ( T,)
c MASS BALANCE:
5 + rh, = rh
= fc v3 3
y c
ENERGY BALANCE:
g conv + g rodn pc [hm;,(r )- h (T.))
m c
CONCRETE THE R Ho-CHEMICA L PATA:
- WEIGHT LOS5 ACC OM PA N YIN G E4CH DECOMPOSITION REACTIO N - Ti:
5 = ({f)Sc S.g = (1 - Z Tl) rh 9
i 3
c
- ENTHA LPY VA RI A T IO N FOR HIXTURE OF GA SEOUSl LIQUI Dl SOLI D DE C O n POSITION PRODUCTS:
o l
h g, y
P
CAVlTY SHAPE CHANGE PROCE DURE o
fk
/
/
~
RAYS MOLTEN POOL
/
+
/
I l
+
I
+
E I
+
\\
\\
I
\\ \\
g
\\/
\\
N-s '
I N
CONCRETE
(
/
/
OUT W A RD NORMALS, ABLATION DEPTH
=
O 5UR FACE POINTS AT TIME i
O SURFACE POIN T AT TIME t + at
IN TER FA CE HEAT TRANSFER 1
TAYLOR
\\N S TA SI L ITY BUBBLE MODEL
[
2 con TIN UO US LAMINAR
~
/
FIL M MODEL
/
'/
3 CON TIN UOUS TURBULENT 3/
FILM MODEL l
{
Re*
'F MOLTEN POOL 5
~
Re cl, OOO~
/
/
k' O O O'~
nnn 4///////////f/
1
~
e,2 e, c
CONCRETE 4
TRANSlTlCN R E Glo N, Oc,- Oc FR0M 2 $
BUSBLE To LAMINAR FILM MODEL 5
TRANSITION R EGl oN, Re,- Re,,
FR0 M
._..-...m.-
~~e.,, u~~
INTERFACE HEAT TRANSFER MODELS HORIZONTAL SURFACE:
J TAYLOR INSTABILITY MODEL:
I Nu = 0.326 RE i
I
/s
/g 2
R s = r,va A A=
p cr h
/ta g (fL fg),
k
,9f3(fc g )
j,,
3 4
TRANSITION REGION:
S
"#ES c
c y
2 INCLINED SURFACES:
2 LAMINAR FILM MODEL:
-1/3 Nu = 0.563 RE
-V3 (X
2 R e = ?' ' > 06 = R RVdi e
Nv= kg ef3 m G(A p )
Me 4
100, RE
= 2RE 5
TRANSIT 10N REGION:
RE
=
7 C
c 3
TURBULENT FILM MODEL:
1 6,1/3 p
Nu = 0.0954 RE Nu AllD RE SAME AS ABOVE, Pa = Dkg
CURRERI__SIAIUS CORCON PilENOMEN0 LOGICAL 110DEUfROGRAPLELEMENT ROUIJNE COMPLETED, INCORPORATED IN CORCON, AtID CllECKED OUT:
MAIN OR DRIVER ROUTINE CORCON DATA INPUT ROUTINE DATAIN GAS MIXTURE PROPERTIES GASPROP TilERM0-CllEMICAL EQUILIBRIUM 0F GAS PilASE GEQUIL TRANSPORT PROPERTIES OF GAS MIXTURES GVISCON DENSITY AND VISCOSITY OF SILICATE MELTS VISRil0 COMPUTER PLOT / MOVIE ROUTINE DATPLOT COMPLETED, CllECKED OUT, AND BEING MODIFIED FOR INCLUSION IN CORCON:
INITIAL P0OL/ CAVITY GE0 METRY POLGE0M MELT / CONCRETE INTERFACE ilEAT TRANSFER lilNTER INTEMP OMLTCON CONCRETE ABLATION AND SilAPE CilANGE CONABL CSilPCNG
.

ML19276F377

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ML19276F377

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Dear Dr. Walker:

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M C W

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