ML20112F967

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Speech Entitled, Aerosol Instrumentation for Marviken Aerosol Transport Tests Presented at 830915-16 Conference. Viewgraphs from Ge/Nrc 840320 Meeting Encl
ML20112F967
Person / Time
Site: 05000447
Issue date: 10/24/1983
From: Makynen J, Piispanen W, Strom L
SWEDEN, GOVT. OF
To:
Shared Package
ML20112F916 List:
References
FOIA-84-220, FOIA-84-221 NR-83-312, NUDOCS 8501160122
Download: ML20112F967 (18)
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S5udsvik Arbetsrapport-Tecmica Re ort Projeni.oentitikat eun - F'ur s t u> -r a t.t si.ve. Daiw en . ,,,s. Urq enn ocn n, _ m. . ..

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. Aerosol instrumentation for the Marviken Aerosol Transport Tests.

L Str5m J M5kynen*

W Piispanen

  • Author attending the conference DestriDution NR E He11 strand (2) NV L Devell (2)

NRS K Johansson NWC R Hesb51 NRS O Sandervig NWS J Chyssler NRS F Carlsson MX5-TAC (15)

NRX J Collen (10) MX5-PB (15)

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,I This report was presented at the 11 th conference of the Gesellschaf t fur Aerosolforschung (CAEF) on September 15,16,198J and will also be published in the proceedings from the conference in 1984. Attached as an Appendix is a reduced copy of the poster that was on display during the conference. ,

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8501160122 040619 PDR

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ST0DSVIK ENERGITEKNIX AB NR-83/312 2

. 83-10-24

'a 3 . -

PURPOSE OF THE PROJECT The primary purpose of the Marviken ATT (Aerosol Transport Tests) project is to create a data base from large scale facilities on the behaviour of vapours and aerosols produced from overheated core materials within typical Pressurized Water Reactor (PWR) primary systems and Boiling Water Reactor (BWR) pressure ~ vessels. The data base is needed to verify theoretical methods which can be and are being used to predict results of postulated core melt accidents for a wide range of geometries and fluid conditions. The existing Marviken test facility has been modified to meet these objectives.

The program has a second objective which is to provide's large scale demonstration of the behaviour of aerosols in

' primary systems.

SYSTEM DESIGN The bqsic arrangement or the hardware components models a PWR with aerosol transport through the hot leg, pressurizer, and relief tank. A tank, simulating a reactor vessel, is designed to have vessel internals which are interchangeable to represent PWR and BWR components. Aerosol material is ,

evaporated using electrical plasma heaters. Extensive instrumentation and multiple sampling stations are used to characterize the system conditions and to measure the .

composition and the transport of the aerosol and gaseous species. Of this instrumentation, only the large acrosol -

samplers ate described in ,this paper. -

STUD $VIK ENERGITEKNIK AB NR-83/312 3 83-10-24 TEST CONDITIONS The aerosol and gaseous species consist of simulated fission products ("fissium"), and in later tests also simulated structural materials ("corium"). The main tests is conducted by injecting the fissium and corium vapours through the bottom of the simulated reactor vessel. In the initial tests however, fissium is vaporized and fed directly into the pressurizer, The vaporized material condenses to an aerosol as the temperature falls during tran port through the system.

The resulting simulations produce the following conditions f or aerosol sampling:

Temperature of gas - up to 800 C ,

Pressure - ambient' pressure Cas flow rate - 0.04 to as 0.5 kg/s, steam plus inert gas and hydrogen

~

3 Particle concentration - up to ~ S00 g/m State of aerosol - liquid droplets and/or solid ~

particles, hygroscopic, may be chemically reactive, highly corrosive, poisonous .

AEROSOL SA>!PLING Aerosol sampling include the following methods: sequential sedimentation sampler, deposition coupons, optical smoke density meter, total particle filter sampler, size fractionating particle sampler, and system wash for depositimi pattern. '

STUDSVIK ENER LTERNIK MS NR-81/112 4 8 'l- 10 -:! 4

  • A sampling train has been designed to provide fractionated samples of the aerosol at various measurement loca t i ons,.

The sampling train is constructed entirely of stainless steel and is designed for sampling up to 800 C. A single piece nozzle / probe assembly is attached either to an 8 plate elutriator' followed by a cyclone cascade, or directly to a 4 stage cyclone train. The elutriator is designed to sample particles above 15 um (D100) but is intended to be used only in later tests where these larger particles ~are expected. The first cyclone flow rate is set to produce a 15 um (D50) cut size. In the later cyclones, the cut sizes are then f or example S.4, 2.4, and 0.87 um at the conditions

~~

of 25 C air, 14.2 1/ min, flow, and 1.0 g/cm particle density (Smith et a l. , 19 79) .

It should be noted that the test conditions provide a signi fica'nt ly dif ferent environment for the cyclones than the "as calibrated" conditions. Calibrations for higher temperature and viscosity are to be made in the.near future.

SAMPLING OPERATIONS Each aerosol sampling station consists of one fractionating sampler and 2 total particle (filter plus prohe) saepling units (Fig 1).

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.STUDSk'1K ENERGITEKNIK AB h*R-83/312 5 83-10-24 Each sampling unit is installed on a moving cradle inside a temperature controlled even. The entire unit is connected to a drive mechanism which rotates at 2 rpm to provide continuous traversing along a single duct diameter. Samples are taken sequentially not simultaneously in order to provide samples over a longer test period. The gas exiting the filter passes first through an air cooled heat exhanger which is temperature controlled to maintain te=peratures greater than 100 C (steam condensation) and less than 200 C (Teflon melts). A single flow monitoring station is connected to the three incoming heated lines and parallel switching valves allow sequential operation of sa=plers.

Sa=pler flow control is monitored using a turbine flow meter in a temperature controlled cabinet. The temperature is maintained above 100 C to avoid condensation. The computer program determines' duct velocity and probe velocity and relays a voltage set for isokinetic sampling. The flow control is then manually adjusted to meet the set point. Data is monitored as real time but activation of the program is by a user defined key at the measurement station computer terminal.

OBSERVATIONS FROM THE FIRST FISSIUM TEST In the first fissium testi steam flow was under 100 g/s

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and temperatures were less than ~ 400 C. Most of the aerosol material was found in the relief tank' water. .

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,. S,TUDSVIK ENERGITEKNIK AB NR-83/312 6 83-10-24 Aerosol instrumentation functioned quite well. Measured

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aerosol concentration was as 80 g/m at the pressurizer outlet and the aerodynamical mass mean diameter was approximately

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5 pm. The aerosol may have consisted of liquid droplets l since at the temperatures of the gas sampled, the Cs0H l

could be in a liquid state. This observation needs to be verified by further testing.

l Problems of corrosion of the stainless steel were not

! severe but the sa=pling train was tarnished and extensive cleaning and polishing was required to prepare the train f or tl.e next test. The filter material was corroded by the l ~~

aerosol sa= pled with the total particulate trains.

  • l REFERENCES
1. Smith, W B Wilson,'R R Jr, and Harris, D B.,

h- A Five-Stage Cyclone System for in Situ Sampling, ES & T, -13, 11, November 1979.

i l -

l FIGURE CAPTIONS Fig 1 Schematic diagram of the aerosoi measurement station.

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GE-NRC MEETING GESSAR SOURCE TERi1 ANALYSIS

. -es fiARCH 20, 1984 BETHESDA,flD

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o

i ,

AGENDA o BACKGROUND o GE PROGRAM PLAN a SOURCE TERM ISSUES i

o SUPPRESSION P00L' SCRUBBING

. SPARC Code Data Comparisons o PRELIMINARY PROGRAM RESULTS O

SCHEDULE l

I 1

( -

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l -

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GESS R SOURCE TERM ANALY$1S BACKGROUND o REASONS FOR STUDY

- VEHICLE TO C0ilCLUDE GESSAR LICENSING

( CONSISTENT WITH DISCUSSION IN DRAFT POLICY STATEMENT)

- FACTOR IN MOST RECENT SOURCE TERM INFORMATION

- HIGHLIGHT IMPORTANT PARAMETERS AND ADDRESS THEIR UNCERTAINTIES-

- PROVIDE PERSPECTIVE ON PROPOSED DESIGN MODIFICATIONS o PREVIOUS MEETINGS WITH NRC STAFF i - FEBRURARY 9,1984 DEFINE SPECIFIC SOURCE TERM ISSUES l - FEBRUARY 22,1984 DISCUSS PROPOSED GE PROGRAM

- FEBRUARY 28,1984 DISCUSS SPARC MODEL-DATA COMPARIS0NS

- MARCH 20,1984

' GE-NRC MANAGEMENT MEETING T0 t

DISCUSS PROGRAM l l GE-NRC STAFF MEETING TO DISCUSS l STUDY RESULTS

- APRIL , 1984 l DISCUSS PROPOSED DESIGN MODIFICATIONS l

S

. i

GE PROGRAM PLAN o APPROACH Perform Sensitivity Studies on Source Term Issues Assess Impact on Fission Product Release and 4

Containment Failure Modes and Timing

. Assess Impact on Base Case Risk l

. Assess Impact of Design iiodifications 1

o SENSITIVITY STUDY INPUTS-

. NRR-Inputs (2/9/84 and 2/22/84 Meetings)

-. BM1-2104: Available Documentation, Peer Review

. BNL Sensitivity Studies

. New Experimental / Analytical Information

~

NRC-IDCOR Interaction Meeting Recent Technical Meetings Marviken.

EPRI-BCL NUREG-0772 and WASH-1400 e

6

t .

SCHEDULE o GE-NRC MANAGEMENT REVIEW 3/20/84 e

a STAFF REVIEW 0F SENSITIVITY STUDIES 3/20/84 o DISCUSS PROPOSED DESIGN MODIFICATIONS 4/84 o DOCUMENTATION OF DESIGN MODIFICATION 4/84

. EVALUATION e

e e

e O

e 8

9 9

e SOURCE TERM ISSUES o CORE HEATUP PHEHOMEN0 LOGY

. Heotup Rotes

. Hydrogen Generation o FISSION PRODUCT RELEASE Fuel Release Core-Concrete Re' lease o FISSION PRODUCT RETENTION

. Primary System Retention

. Suppression Pool Scrubbing I

o SUPPRESSIdNPOOLBYPASS o SITE POPULATION

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j

+ .  !

I l

SUPPRESSION POOL SCRUBBING i (SPARC) l 0

MEETING AT PNL - 2/28/84 - GE/EPRI/PNL/NRR CONSULTANTS o

MEETING PURPOSE - REVIEW SPARC CODE EVALUATIONS OF EXISTING GE AND EPRI DATA o PRINCIPAL GE CONCLUSIONS

. SPARC Underpredicts Most Data Confirmed by PNL Calculations

. Identified Changes That Improve Model Predictions O SATURATED P0OL DATA

. SPARC Predicts Little or No Scrubbing for Saturated Pools

. DataShowsSaturatedPeelScrubbingasGoodor Better Than Subcooled Pcol Scrubbing PNL Modeling Phenomena to Account for This Effect a GE CONCERNS -

. SCARC Changes May Not be Reflected in GESSAR Review

F~ ' . . .

PNL CALCULATIONS SPARC MODEL VERSUS SCRUBBING DATA CROSS - VNC .

sounRC - rear 10'-

10'-

5 e-l12 5 .

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10 10 10 f1CASURED DCCONTN!!NRTION FACTOR e

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,, PRELIMINARY PROGRAM RESULTS o GESSAR RISK RELATIVELY INSENSITIVE (< FACTOR OF 2 ) T0:

- CORE HEATUP~

- HYDR 0 GEN GENERATION / 0XIDATION MODELLING

- PRIMARY SYSTEM RETENTION

- EARLY RPV FAILURE

- CONCRETE COMPOSITION o GESSAR RISK MOD $RATELY SENSITIVE ( FACTOR OF 2-10 ) T0:

- LATE TELLURIUM RELEASE

- HIGH POPULATION DENSITY SITE

- SUPPRESSION POOL SCRUBBING o CONCLUSION:

- UNCERTAINTIES IN SOURCE TERM ISSUES APPEAR UNLIKELY TO RESULT IN SURPRISES AFFECTING GESSAR 9

9 e

. . . . . . . . . . . . . ._ .. . .J

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