ML19289E380

Minutes of 781206 Meeting of ACRS Subcommittee on Advanced Reactors in Washington,Dc to Discuss NRC-sponsored Research on Safety of Advanced Reactor Design.Concludes Aerosol Release & Transport Programs Are Valuable

ML19289E380
Person / Time
Issue date:	03/10/1979
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-1602, NUDOCS 7904170330
Download: ML19289E380 (38)

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j//o[<J9 MINitrES OF 'IllE ACRS SUBCOMMITTEE MEET. IIG ON ADVANCED REAC'ITRS WASHINGTON, D.C.

"hOh DECEMBER 6, 1978

%e ACRS Subcommittee on Advanced Reactors held an open meeting

1. [I on December 6, 1978, in Room 1146, 1717 H St., N.W., Washington, D.C.

W e purpose of this meeting was to review matters related to the NRC-sponsored research on the safety of advanced reactor design.

The aerosol release and transport program was of particular interest.

Notice of the meeting was published in the Federal Register on October 17, 1978, October 31, 1978, and November 21, 1978. Copies of these notices are included as Attachment A.

A list of attendees for this meeting is included as Attachment B, and a schedule for this meeting is incitried as Attachment C.

Selected portions of the meeting are also included as Attachment D.

A complete set of handouts has been included in the ACRS files. tb written statements or requests for time to give oral statements were received from menbers of the public.

The meeting was attended by Dr. M. Carbon, Subcommittee Chairman, Dr. D Moeller, Subcommittee member; Dr. R. Savio, ACRS Staff; and Dr. M. First, ACRS co7sultant. S e Ineeting was opened at 1:30 p.m.

with a short executive session during which Dr. Carbon summarized the schedule and the goals for the day's meeting. W e meeting was held entirely in open session and was adjourned at 5:30 p.m. on this day.

INTRODUCTION - C. KELBER, NRC/RSR Dr. Kelber gave a brief overview of the NRC's aerosol release and transport program. Dr. Kelber indicated that the program was cen-prised of three majoc efforts:

(1) the developnent and quantification of improved aerosol transport codes and supporting basic properties measurements, (2) tests of sodium and fuel aerosols and their mixtures THIS DOCUMENT CONTAINS P00R QUAllTY PAGES 7904170 3 30 n ~. :n

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4 e Advanced Reactors December 6, 1978 in the NSPP for aerosol code quantification, as.d (3) developnent and testing of models of aerosol behavior in an ICDA bubble in the Fuel Aerosol Simulant Test (FAST).

Dr. Kelber stated that the budget reductions instituted for FY 80 would require cutbacks which might be accommodated by following the recommendations of the Budget Review Committee and terminating the work in the aerosol release and transport program. We impact of this would require the termination of the CRNL work at the NSPP (Nuclear Safety Pilot Plant) during early FY 80.

Dr.

Kelber indicated that he believed that this would result in the ter-mination of an element of this program at the p int when the technical verification of key assessment methods of aerosol transport was within sight.

Dr. Kelber indicated that the developnent of source terms has been de-emphasized in these programs to allow the greater effort to be put into the area of aerosol transport effects. Dr. Kelber indicated that it was his belief that these programs were productive and important and requested that the Committee review these programs in light of possibility of an early termination.

OVERVIEW OF THE AEROSOL RELEASE AND TRANSPORT PROGRAM - M. SILBERBERG, NRC/RES Mr. Silberberg summarized the Aerosol Release and Transport (ART) program.

He noted that in 1973 the IMFBR aerosol research was abandoned by the AEC, leaving the program in the following state of developnent:

(1) The aerosol code'HAARM-3 had been completed and the last major improvement of the code had been made in enout 1970. Verification of the code at that time consisted of adjusting two key input coefficients such that the code would match the results of existing experiments.

(2) No work had been started in the area of the developnent of the ICDA source term.

We FETF source term (100 grams of plutonium or about.003% of the core) represented the state-of-the-art.

(3) Co-agglomeration of fuel and p_5

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r Advanced Reactors December 6, 1978 sodium.had been demonstrated by a few tests in a 6-foot diameter vessel and in a 30-foot diameter vessel. %e tests in the larger vessel were inconclusive, principally because of the small quantity of UO used in 2

the tests. %e ART program-was initiated in 1974 and has developed to the point where facilities and a team of specialists have been acquired.

Mr. Silberberg indicated that the program was presently producing data and methods which would establish the basis for the reliable assessment of the radiolcgical consequences over a broad range of postulcted acci-dents conditions and for the resolution of key safety issues. Mr. Silber-berg stressed that the RES believes that the research team was the most valuable resource and represented an important investment which would be difficult to recover once lost. We results of the ART program are being applied in the FFTF and the proposed CRBR programs.

Mr. Silberberg noted that, for the FFTF, the HCm source term was not an issue in the FSAR. For CRBR it is proposed that 1% of the plutonium in the core should be used for a source term and that for assessing con-tainment margins a 10% release depleted to 1% by attenuation mechanisms should be used. We RES Work on a ICM source term has not yet progressed to the point where the source term could be verified.

With regard to the transport of aerosols within the containment, Mr. Sil-berberg indicated that the effective co-agglomeration for aged aerosols (where Brownian agglomeration is not the dominant mechanism) has yet to be assessed. Presently ARSR interx3s to maintain a level of funding to the NSPP in FY 79 and FY 80 which is large enough to complete the basic m' atrix of proposed mixed sodium and fuel aerosol tests and also to

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continue to support the analys,is and verification tests being conducted at BCL. To do this, ARSR will defer the work on the core melt aerosols in a core melt environment and the aerosol behavior of specific fission products.

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_.__ ;er 6, 1978 ARSR has had numerous exchanges with foreign countries under their bilateral agreements. tere is a general consensus on the unresolved areas of aerosol technology and their relative priorities.

ART PROGRAM ACCOMPLISHMENTS AND DIRECTIONS - J. I.ARKINS, NRC/RES Mr. Larkins summarized the conclusions of the state-of-the-art report prepared by the Committee on the Safety of Nuclear Installations (CSNI - an international group of experts in nuclear aerosols). We report covered nuclear aerosol formation and characterization, aerosol processes inside containment, and the computer modeling of aerosol processes. We report concluded that:

(1) analysis methods are at an advanced state of developnent for predicting nuclear aerosol trans-port in IRFBR containments following a p)stulated severe accident; (2) aerosol processes modeled in INFBR codes are applicable to the analysis of postulated IMR core melt accidents; (3) the main difference in modeling between the various aerosol codes can be grouped into three categories:

(a) restriction to a log-normal particle size descrip-tion; (b) restriction to constant values for particle and process coefficients; and (c) the absence of condensation; (4) results of limited' sensitivity analysis for postulated working accidents established solely for the comparison analysis indicates that the uncertainties in particle and process coefficients can lead to uncertainties of a factor in between 2 and 10 in aerosol leakage from the containment; (5) aerosol predictions for a postulated working accident using five different codes agree to within the factor of about 6 for aerosol leakage; (6) an important question in all of the aerosol codes. is that of continued agglomeration of the aerosol species of different materials and that very little data is available to verify the assumption over a range of, interest to accident analysis, and (7) the methods in data for quantitative prediction of nuclear aerosol source term for postulated severe accidents are not well developed. W e CSNI further recommended that the following items be considered as high priority research projects in industry:

(1) establish aerosol code verification procedures to aid in determining an acceptable end point for aerosol tests;

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, ember 6, 1978 (2) determine the effect of the ma'in differences in acrosol code assumptions particularly log normal size distribution and constant particle coefficient; (3) verify experimentally the applicability of the aerosol coagglomeration assumption (4) extend ongoing mea-surements of process coefficients for single species aerosol agglome-rates to mixed species; (5) confirm and quantify conserative margins in current release assumptions through research on source terms; (6) quantify the modification of particle concentration and characteris-tics during leakage from containment; and (7) assumptions regarding condensing vapor and droplets used for particle growth rate need to be experimentally qualified.

Mr. Larkins noted that the ART program as developed over the past three years covers most of the concerns in the CSNI report and could, at the current funding level, be resolved in the 1980-81 time frame as the bulk of the issues have been identified on aerosol behavior in containment.

The source term work is not as far advanced as the aerosol transport work. Analytical models used for the EDA source term are similar to those used in SIMMER and are geared toward describing the FAST experi-ments and describing what happens to the aerosol in the T DA problem.

In the aerosol transport work, aerosol property measurements have been made and the models used in the HAARM code be improved to provide a much better protection of experimental results.

Intermediate scale tests have been conducted in the M3PP at CENL and the CSTF at HEDL.

Work is also being done with mixed aerosols to resolve the questions on co-agglomeration and improved models for collision efficiency are being developed. 'Ihe NRC expects with their current program and the continued cooperation of DOS to be able to verify the RVaM code within the next two to three years at the present funding level. A small study is underway which will look at chemical composition of the aerosol which is formed in the primary system, in containment. 'Ihis work is directed toward examining the question of whether more soluable forms of uranium and plutonium more soluable than the uranium and plutonium

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y Advanced Reactors December 6, 1978 oxides could be formed during an U4FBR accident and whether these could result in increased dose.

We contractors involved in the ART program and a summary of the scope of their work is given on page 1 of Attachment D.

Recent program accomplishments are summarized on pages 2-5 of Attachment D.

OAK RIDGE NATIONAL IABORATORY - AEROSOL RELEASE AND TRANSPORT PROGRAM -

T. KRESS, ORNL Mr. Kress summarized the ART program activities at CRNL. Se program activities fall into two broad categories: those directed toward sttriy-ing the in-primary vessel behavior of high energy (HCDA) fuel and those directed toward studying the behavior of released fuel and sodium oxide aerosols in the containment (HAARM-3 qualification). To conduct experiments ORNL has used two specific techniques: the capacitor discharge vaporization (CDV) technique and the plasma torch technique. Se.CDV technique has the capability of depositing large (>3500 joules per gram) energies in fuel samples. Se plasma torch technique is used for producing high concen-trations of fuel aerosols in large vessels and is used extensively in the study of aerosols in simulated containments. Mr. Kress showed a short film of CDV experiments in argon, in a vacuum, and in water. UO f"*1 2

samples were used. Se CDV technique is used in the CRI-III experiments (argon atmospheric experiments) and in the FAST (sodita) experiments.

We CRI-III and the FAST facilities are described on pages 6-9 of Attach-ment D.

Some of the results obtained from experiments at these facilities are summarized on pages 10 and 11 of Attachment D.

We NSPP facility is used for the experimental verification of the HAARM-3 code using mixed species aerosols under secondary containment conditions.

Description of this facility is given on pages 12-14 of Attachment D.

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. Advanced React ember 6,'1978 Questions were raised as to the relevance of the single component soditan aerosol experiments and to the high sodium aerosol concentration used in some sodium and mixed components experiments. %e sodiun aerosol experi-ments in question had been performed in other facilities and the results were well known. ARSR stat'ed that these experiments were performed to develop the techniques used in the ARSR facilities and were used as reference experiments. %e sodium aerosol uncentrations in question were so high as to allow the aerosol to exist only for a very short time. ARSR stated that their intention was to study the conditions which existed early in the accident sequence and agreed that these conditions were beyond the range of conventional aerosol sttxlies.

%e relevance of experiments to verify gravitational coagglomeration with aged mixed aerosols was also questioned. It was felt that the existence of this effect was self-evident. ARSR felt that in the licensing process there was a need for verification.

BATTELLE COLUMBUS LABORATORY'S AEROSOL s DE DEVELOPMENT AND QUALIFICATION -

V J. GIESEKE, BCL Mr. Gieseke summarized the code developnent work at BCL. W e HAARM-3 code exists and has been used for use time. % e REFERENCE code is currently being developed at BCL. BCL's programs call for developing the code to level of the current HAARM-3. %e capabiliti 1 of the code will then be expanded to enable the user to treat multiple zones and mixed species.

Mr. Gieseke discussed the capability of existing codes.

Rese are summarized on page 20 of Attachment D.

Aerosol property measurements are being made in a Hillikan cell apparatus at BCL. Sodium and uranium oxides compounds are being sttxlied. BCL has used the HAARM code to predict the results of a number of existing experi-ments. Se results of some of these comparisons are shown on pages 21 and 22 of Attachment D.

BCL has sttx31ed the sensitivity of the HAARM-3 computer code to the various input perameters. A ranking of the sensitivity of the code to the input parameters is given on page 23 of Attachment D.

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Advanced React amber 6,1978 SANDIA IABORATORY - AEROSOL NORMALIZATION - D. ELRICK, SANDIA Mr. Elrick summarized the aerosol source normalization in experiments being' conducted at the Sandia Laboratory. We purpose of these experi-ments is to compare the properties fuel debris produced in-pile with that produced in out-of-pile experiments. Se ACPR in-pile experiments and the out-of-pile experiments at ORNL are being used for standards. Experi-ments will be run in the ACPR utilizing conditions similar to those pro-duced in the CRNL out-of-pile tests. Sampling, photography, and photo-metrics techniques have been successfully demonstrated for in-pile experiments. It is expected that data which can be used to compare the characteristics of fuel debris generated in-pile and out-of-pile will be available in 1979.

MXJND IABORATORY - CHEMICAL CHARACTERIZATION OF AEROSOLS - J. LARKINS, NRC/RES The objective of this program is to determine what types of reaction products will be formed and in what quantities from the interaction of mixed oxide fuel, soditra, stainless steel, fission products, and the atmospheric consitituents in the containment building following a simulated HCDA. mis effort was motivated by concerns that under ICDA conditions, sodium uranates and plutonates could be formed. Rese compounds are more soluable in biological fluids than the dioxides by a factor of 10 to 100. mis increased soluability, therefore, would increase the biological effectiveness of the plutonium in dose calcula-tions.

Aerosols are being generated using CDV and laser techniques under simulated ICDA conditions. Experiments have been performed with sodium dioxide and the formation of sodium uranate has been observed.

Current work is directed toward quantifying the test results.

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C04CLUDItXI DISCUSSION Dr. Kelber indicated that he believes that the aerosol release and transport programs were valuable and were producing useful results and that these programs had been developed to the pint where they were productive and that much would be lost if they were terminated and restarted at a later date.

Dr. Kelber noted that the results of these programs would be essential in the design of hardware such as sand and gravel filters for U4FBR containments.

Opinions were expressed by the Subcommittee and the Subcommittee consultants that, although they believe that small cuts could be absorbed in the programs, the work is valuable and should be continued.

'Ihe meeting was adjourned after this session at 5:30 p.m.

NOTE: For additional details, a complete transcript of the meeting is available in the NRC Public Document Room, 1717 H St., N.W.,

Washington, D.C. 20555, or from Ace-Federal Reporters, Inc.,

444 North Capital Street, N.W., Washington, D.C.

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Street NW Washington D.C. 20555.

Omer matte 'wM may be of a cember 1.197P.

All other enatters pertatning to this predecisional na "elevant to reac-Summary etnutes:

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tor operation anafng activities the Committee Man reme Coordinator, nounced on October 17.1978 (43 FR may be 11owing this ses-Division of and; Administrative 47802), and October 31.1978 (43 FR sion.

Management. Room

8. National Science 50163).

ybundation. Washin n D.C. 20350.

Persons wishing submit written Purpose of Subcommit :fo provide advice Dated: November 15.1978.

statements.

regulatory guide and recommendations rning support for research in Cogiou Science.

JoEN C. HoTLs, 1.E 1.

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JdcGory Committee ing a readily rep ble copy to the Kanagement Chicer.

subcommittee at e sinning of the Nr day. Decem6er f n-s A.Ar. to 3 CPR Doc. 78-32545 Pued 11-20-78; 8:43 ami meeting. Hower, to that ade-P.Jr.

t quate time is a le or fun consid-Review and cornpar a >f declined pm.

eraMon el 2 ents at Me posals (and supportin doet mentation) with (7590-01-M]

meeting, it is le send a readt-succeanful awards er th Software Sys.

ly reproducib oopy of e comments tems Setence Pro inci ding revte, of soar comunfrru ots alACT SAFE-as far in ad of meeting as peer review materi and her prtruesed o RDS $UsCoAunlTTIE oil TotY material. Prepara a of report based A VTfES k

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11 a.rn.-B efing by Mr. E t curus. published in t eta 1 RuotsTzm on Such ents shall be t.pon Head. Css

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docum ta on fHe and availab for,

12 noon-In accordance th the procedures 1 p.m.-

loo of Compu sciones outline in th Ractsrsa on pubife pection at the NRC bile Institute's.

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by members fthe recordings er informatjon Reason f clostns: The Subcomm. tee wG will be pe tted only uring those top!

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be reti ins grants and declinati > Jack. portions the aneeting en a tran-mee has been canceled or ets wh h contain the names of a $ cant script is ing kept, and qu ons may dule the Chartman'S ruling on

$se inf$rm t eo tai ed be aske only by members the sub-d emmmt qu for the opportunity to det! d proposals. This session also its consultants, stafL oral tements and the time RDot inclu a review of the peer review Perso desiring to make e state-men should notify the the for can be obtahd by a W men uon pertaining to appticants. '

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by section 805 of the Community Ser-32.the Commfamion has concluded that ments. ~ ~

vices Act to advise the President and an environments' anpact statement For further detans wfth respect to the Director of the Community Set-for this particular license renewal was this action, see (1) the app 1! cation for vices Admini.tration on poucy matters 'not warranted because there wC1 be no amendment dated June 13, 1978. (2) arising under the k'iministration of significant environmental impact at. Amendments Nos. 35 and 17 to Lt.

the Act and to review the effectiveness atributable to the proposed action The censes Nos. DPR-53 and DPR-49, and and operations of prograras ander the uswirornnental

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• sonEsble for public Inspecuon and Evaluation. AH of these items are Records shall be kept of an proceed-hepring at the Commission's: Pub!!c avaf]able for public inspection at the Ings and shad be avanable for puhuc Document Room at 1717 5 Street.

inspection at the office of the Nation-NW., Washington D.C.

Commfuton's Public document Room.

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1717 H Street. NW Washington, D.C.

portunity.

. Dated at S!!ver Spring, Md. this 23d and at the Calvert County L!brary, day of October 1978.

Prince Frederick. Md. A copy of items Waz.rza B. Qurrsca the Nuctsar Regulaton h -(1) and (3) may be obtained upon re-Krecutive Director.

quest addressed to the UA' Nuclear (FR Doc.18-30601 F0ed 1040-18; s:ta am)

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held on Wedr.esday. December 8.'1078 in Room 1048.1717 H 8treet. NW.

The U.B. Nuclear Regulatory Com-Washington, D.C. 20555 to continue its mission (the Comm!nton) has issued IDocket No. 54 ti13 review of matters related to the NRC l

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,, p The agenda and an othe matten pertaining to me muung nrnain ute ed in Calvert County, Md. The amend-mission (the. thmmia=im4) has lasued same as announced in above cited FED-ments are effecure as of the date of is-Amendment No. 41 to Faciuty Operat-a ing L! cense No. I2rRC. Issued to su.g.nce'am~en6ts W n "I4ch. Consolidated Edison Co. of New York.

anal Rsosstra notices.

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nical Specifications to delete the r,.

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ment Charcos3 ytter Dousing System. The amendment is effecsJve as of the The appDestion for the amendments date'of lasuance.

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WISIC88. CommatCIAt NUCLEAR FUSL FAB

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the Commfuion's rules end regula-The application for the amendment PA.

.- t glons kl 10 CFR Chapter I. which are contpUes with the standards and re-set forth in the 18e==== amendments. apuirements of the Atomic Energy Act 13seene No.5Na6-Ist Prior public actlee of these menend-af 1954. as amended (the Act). and the ments was not required since the raammt-ton's rules and regulations.

The U. FL Nuclear Regulatory Com smendmenta do wot tavolve a slanft). The Commianfaa has made appropri-mission (the Commission) has renewed eent hasards consideration. w.

.ste findings as requ! red by the Act and 80ecial Nuclear Material fie*n=e

'The Commf= ton has.d.asermined the r%=mi-ion's rules and regula-SNM-1(S for the ocatinued operation that the tasuance 'af SKese amend-tions kl 14 CPR Chapter I..which are of the B&W Nuclear Fuel Fabr4**Maa menta viu not result ininy significant setjforth in the 11eense amendment.

~ Plant at Apo!!o Pa.

environmental knpact and that pursu- (Prior public nouce of this amend-The Commission's Divisico of Puel ant to 10 CFR 51.5(dX4) an environ-ment was not required since the Cycle and Material Safety has pre-mental tmpact statement. or negative smendment does not involve a signifi-pared an envirc unental ampact ep-declaration and enytrnnmenf at tenpact tsant hasards consideration.) ' ~*

PBERAL Geotsfet, tot 4R, too. 34t-*WtsaAY, OC70esa et,1ers

~

y.,

(

H r y,}-

', - c.y

..'.e.-

b

~, -

7

.,3 47802 NtlmGS plants of the Swank Refractories Co. ' - 31sned at Weahington. D.C:, this 9th amount of Umar requestedt.me hdprid-The Invest!sation revealed that only day of October 1Ma-ual's qualtfieauens to speak on the clay products are produced. '

R.maY J. Qu.asAN, subject matter. 'I7te appIleaflen shaU The notice of investigation was pub-Jettsa Director,0lftce of also inchade a statement justifyks Ushed la the Fznsaar. Ractsrsa on Foreten Keonostic Researck why a written presentatten would not June 20.1978 (43 FR 26499). No pubUe tyk Doc. 75-2s158 yued 19144s; 248 r.at-suffli The Chairman reserves the hearing wn requested and none was I,.,i right tn decide to what extent pubHc.

oral presentation will be permitted at held.

.., ~

The Infonnation upon ubich the de ' [4510-30-MF ' N the conference. Oral presentauens termination was made was obtained ahan be Itatted to statements of fact g

- - pog principally from officials of Swank Re-fractories, its customers, the UA De-

.and views and shau not inchade any.

FOt*ET questions of Cnmmtmfon members or '

partment of Commerce, the U.S. Intm atomans,,

other partleipants unless these ques.

.~

national Trade Ca==f== tan, ladus$ry.., Pursuaint to the provtslons of the tions have been speciDeally approved analysto und Department files.

yederal Advisery Committee Act Pub. by the Chairmaak In or ter to make an affirmative de-L 92-463; 86 Stat. 770) notice is Minutes of the meeting, working terminatico and issue a cert 10cauon of hereby given that the National Coca-papers, and other documents prepared e!!gibility to apply'for adjustment as-mission for Manpower Policy will co-for the conference win be avaDable fos' sistance, each of the group eligibuity sponsor, together with the UA De-public h==4 fan 6 working days after

• requirements of section 222 of the Act partment of Labor. Bureau of Interna. g,gh, g,g,,gan.s head- '

must be met. Without regard to tional I4bor Affatn. a contennos om e arters located at 1522 E Street NW '

whether any of the other criteria have Q Id a

nf Suite 300, Washington. D.C.

been m t.

fonowing cruerlon has ence P.aom. Room 8-2504. U.S. De-Signed at Washington. D.C this ella.

D04 partment of I4bor. 200 Constitution ~ day of October 1978.

thma lacreaams of tenoorts et stur.las tlke or Avenue NW., Washhyrton, D.C. The -

eineur compeutsve with arueles produced meettos wtn begin at. 9 a.m. and ad.

Isaass.v.SawsmA.

by suen worsers' ttrm or an appropriata sub.

Journ at 5 p.nL The agenda will be, Erector. #stional Cmmission devtaion thenot contributed tmportantas to concerned with idenuising and explor.

forKampoiserPoliest

'*3,,jg, d

ing the employment effects of interne.

tyR Dec.15-at191 FBed 161618t kesad :

'"*8 tional trade.

i

ducuan, The National Commfanion for Man.

Evidence developed during the inves-power Poucy was established pursuant

[7 p q tigation revented that clay refractory to title V of the Comprehensive Em-producta are used in the molten stages ployment and Training Act of 1273

. NUCLEAR HGULATORY of metal production by the steelindus- (Pub. L 92-203). The Act charges she COMMIS$10N try. Clay refractory producta cannot Commt=Aan with the broad r==panat-be considered like or directly competi. bility of advising the President, the Asvuoav connutras ces asAcros sass.

tive with steel.

Congms. W 8ecntary of I. abor, and GUAtoSa Sut(CAAMirTEE 000 ASVAseCID other Poderal agucy adIntnistrators REA N

'!he istic of importa to the domestle production of clay refractory products p,,h[n] g O

• • p an gg,,,,,,

has been less than 1 percent from 1M2 charsed with reporuns annually to h ACHK kMthe on M to 1977 and in the !!rst quarter of the President, and the Congress on Rs vanced Reactors will hold an opea 1978.

findings and reconunendations with meeting on November 1.1978. In' Room The Department conducted a su.vey respect to the Nation's employment 116*l* 1717 R Street NW., Washington, of some of the customers of clay rr. and trafntng polleies and programs.

D.C. 20555. W conunne na miew of fractory products of Swank Refractor-Members of the general public er inauera related 2 me NRCW les Co. Only one of the customers re. ~ other lateres m individuals my ported purchases of imported refrac. attend the conference. Members of the research on the safety of advanced re-tory products in 1977. That customer public desiring to submit written state.

actor designs.

menta 2 the Canznission that an ged In accordance with the proceduns stated that the type of refractory mane to the agends may do so, pro.

outlined in the PEBs1A1. RectsTsa ce product imported was not avaDable vided that such statementa are in re.

October 4.1978 (43 FR 45926), oral or from Swank and continued to state that the reduction in purchases frons

$o wri en sta aments may be presented ter da by members of the pubuc. recordings

. Swank in 1977 compared to 1978 was before and 7 days aft r the confer.

win be pemiued only during those caused by a shift to other domestle enee.

sources. All of the respondents stated Add!UonaHy. members of the gener-poMons of h meufng when a tran.

that importa of refractory products al pubile may request to make oral script ts being kept, and quest!ons may are not adversely affseting the domes-statements to the Commtazion to the be asked only by members of the Sub.

tac industry; extent that the time available for the committee. Its consultants, and staff.

conference permita. Such oral state

• Persons destring to make oral state.

ConcLosroW mar.ta must be directly germane to the ments should notify the Designated anno Peders! Employee sa far in advance as After careful review. I determine gns st sul mitted h

that all workers of the Johnstown and.,re,ctor of the cammtemion. 3 days; practicable so that appropriate ars rangemets can be inade 2 aHow the Clairton (IArge). Pa, plants of the before the conference. This appI!cs.:

Swank Refractories Co. are denied eU* Uon shan identify the following: Thej necessary tim during the meeung for gibGity to apply for adjustment assist-name and address of the appucant; the such statements.

~

ance under Utle II. chapter 2 of the subject of his or her presentadon and

.The agenda for, subject, meeting Trade Act of 1974.

Ita relationship to the agends; the shan be as foDows:

pgomAt BE04 STER. Vot. es, fee. Set-,rutSDAY, ocromR 17, Tsrs i

~

e.

5 47803 pe00CES provisions of secuans 13 sad 1kd) of

Wiessenaw.Nov-= 1.199e[ -

-be saked only by maembers of the sub.

committee. Its musultants, and staff. the 1934 Act.

2. On AprU 35,1978, pursuant to a Persons desiring to make oral state-merger with '11tyssen Acquisition D

ments should nodfy the dedsnated Federal employee as far in adeacce as Corp., afie Appincant became an todi-he Bubcotnarttee smay meet in ex-practkat'e ao that appropriata ar* rect whour owned subsidiary of Thys-rangements ma be made to aDow the sen A. O., a West German corporation, eentive n==8an, with any of its consul.

3. As a consequence of the merger tents who anny be present. to explore neessary time during the meeting.for the dw's wnmnn and preferred and exchange their prealminary optn. such statements.

tons regardfas mattaes which should The agenda for-suW smeedag shares ceased to be outstanding on k considereddwtag the eseecrag and shan be as foDows:

April 25,1978 and its 5% percent con.

to formulate a report and recommen-mtable stabadinatad &bentures wem dauons to the fuD Cosamittee

. Wmmunav.Nonames 1.1978 redeemed on May 26,1978.

At the conclusion of the executive a:n a.as. ourn, faz conca.ostos ce sussress In the absence of an execupWn. Ap-session, the Subcommittee viu hear 3.he =ha'> may meet in ese plicant is required to fue reports pur-presentations by and hold discussions asustan, with any of na consultanta who may suant to sections 13 and 1Md) of the with representatives of the NRC staff, and their consultants, pertinent to the be present, to explore and eachsnse their 1934 Act and the rules and regula above toplas. The Subcommittee may which should be esastdered durtas the thereunder for the balance of the pretemenary opinaans rosarding matters then caucus to determine whether the fiscal year ending December 31.1978.

Appikant believes that its request for aweuns.

matters identified in the initial session have been adequately covered and g,, h* %us,e an or11er exempting it from the provi-t cations m

whether the project is medy for and hond discussions with reorsmentaures of sions of sect!5ns 13 and 1Md) of the the NRC staff, and their consuhanta, peru. 1934 Act is appropriate in view of the review by the full Committee, nent to the agenda nama. 'Ibe sur===tt.

fact that Appucant believes that the Further tuformation regartling see mar than caucus to detarmine whether topics to be discussed. whether the the matters ndentined to the initial aa-taa mae. anat, and upense inmind b n.eeting has been amnewled or resche. hag two adequatett conrad and to formn-papantion of addiuonal periodic m duled, the Chairtnan's rullag on re. nose a moort and m -

" " - - to the pets would be AmoWh to any quests for the opportunity to present fan benefit to the public.

=

l oral sta! Aments and the time aI!otted Further - Information regarding For a more detaHed statentent of the I

therefore can be obtained by a prepaid toples to bt. icuased, whether the taformat$on presented, au persons are talephone enn to the Designated Fed-Ineeung has u.n canceled or reache. referred to asid app!! cation which is esal Dnployee for' th!s ineeting. Dr.

duled, the chairman % ruung on re. on fDe in the offices of the ranm m te.

Richard F. Savio, telephone 202-d'e4-quests for the opportunity.to present oral statements and the une anotted alon at 500 North Capitol Street NW 3267. between 4:13 a.m. and 3 p.m.

Washington. D.C.

s.s.t.

therefore can be obtained by a prepaid Notice is further siven that any In-Dated October 12.1778.

telephone call to the daf*aabd Fed-terested person not later than Nevern-

- Jour C.Earta-erst employee for this meeting. Mr.

4. AdelsoryCommittee Robert 1. Wright. Jr telephone 202-ber 3,1978. maar submit to the Com-mission in writing his views or any Manaoement Omcer.

634-3314 between 8:15 a.m.and 5 p.m substantial facta bearing'on this appu-fyR Dec.15-as:14 Fuad 10-to ts; a:45 am3 e.s.t.

dation or the desirstr.11ty of a hearing Dated Ortober 12,1978.

thereon. Any such communimuon or I

aquest shald be addresset 8eem

,yg,,

tary. Securium and rxchange Com-NNM afenseement omeer.

GUARD $s N oN asAc?os W.

[yR Doc.Ts-3e319 FUedto-to 'is; a:45 aml NW., " Washington. D.C. 20549, and aansosy coeurrus oN anacros sars.

abould state briefly the nature'of the EAtsoses interest of the perrn subas!tting such '

M informauon or requesting the hearing.

baseans

^

the reason for auch request and the The ACR8 Subcommittee on Rome.

$5CUtfTES A)S) EXCHANGE lasues of fact andlaw raised by the ap-ter Operations. w!D hold an open COMfA11 MON 3 cation which he desires to contro-eneeting an November 1,1978. in Room 11 vert. Fernons who request a hearing or 1944. 1717 E Street NW., Washinston.

D.C. 306&5. to review NRC Office of

'u& nan. Fre.70s No. s.e3s; Fue ase. st.

advice.as to whether a hearing is or-Research pro-dered w01 receive any nouces and aft 3 J.[. iuclear.11egulatorysrsms being conducted by the Re-EUse CD.

l orders issued in this matter, including the date of the hearing Of ordered) eserch Support Branch, and will hear gg,,i,,,g q - y,,4 g _., ese say postponements thereof. At. Any a briefing by representatives of the NRC Division of Operaung Reactes t!aie after said date, an order granting anastig l

concerning its poucles and scuvtua.

Octonsa 4,1978..

"#9" r

Notice of this meeting was pubushed Motice is hereby stven that the Budd er the September 31.1978 (43 FR 42826) as a Co. (" Applicant **) has filed an appucs-

• tien pursuant to section 1300 of the 'mouan. *For the Commterion, by the i

34547 meeting. October 31 anJ Novem-Securities Ezr hanne Act af.194 as af Corporstion Finanr* p'ursuant to ber L -

• Ja accordanse with the procedures amended (the 1934 Act"k=*fna an 8-exemption freen the sequb oats to delp authority.

l

• outlined ki the FspesaL Raatsrat anOctober 4.1976 (45 FR 45926). oral or Sie reporta pursuant t

===+8 ann J

13 Gaoact A.Frtzanorous, written statements may be presented andikd)of the 8'rehange Act.

Secretary.

by miembers of the public, recordings 4he Appucantstates,inpart:.,

IFR Doc.14-as12e Fusd to-ts-Ts; s:45 aml win be permuted only during thcee

.1. 'Ihe Appucant se a Pennsylvania peruens of the meeting when a tran-earporation subject to the reporting script is being kept, and quesuons may g

\\,

3,

.:-* /

i

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_ rh*,,,. 1 c-,,

i

~

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r.: J.;h;.

+. e..

i

_i

ACRS SUBCOMMITTEE MEETING ON ADVANCED REACTORS WASHINGTON, DC DECEMBER 6,1978 ATTENDANCE LIST ACRS M. Carbon, Chairman D. Moeller M. First, ACRS Consultant R. Savio, Designated Federal Employee NRC STAFF M. Silberberg L. Rib C. Kelber J. Larkins J. Long OAK RIDGE NATIONAL LAB.

R. Adams T. Kress BATTELLE-COLUMBUS J. Gieseke SANDIA LABORATORIES R. Elrick A66achmenb B

PRESMTATICN SGEDULE ACRS SUBCOMMI'ITEE ON ADVANCED REAC'IORS

, SASHI!EION, DC DECEMBER 6, 1978 Approximate Presentation Time Time 1.

EXECUTIVE SESSICN 10 mins.

1:30 p - 1:40 p 2.

OPENING REMARKS (C. Kelber) 5 mins.

1:40 p - 1:45 p 3.

AEROSOL RELEASE AND TRANSPORT PIOGRAM BACKGm (M. Silberberg) 15 mins.

1:45 p - 2:00 p 4.

ART PROGRAM ACCOMPLISHMENTS AND DIRECTION (J. Larkins) 10 mins.

2:00 p - 2:10 p 5.

ORNL - ART PROGRAM (T. Kress) 90 mins.

2:10 p - 3:40 p 6.

BCL - AEROSOL COOE DEVEIOPMENT 40 mins, 3:40 p - 4:20 p 7.

SANDIA - AEROSOL IORMALIZATION (D. Elrick) 10 mins.

4:20 p - 4:30 p 8.

!OUND - GDlICAL GARACTERIZATICN (J. Larkins) 10 mins.

4:30 p - 4:40 p 9.

GENERAL DISCUSSICN 4:40 p - 5:30 p

1 CONTRACTORS IN ART PROGRAM UNIVERSITY OF UNIVERSITY OF MISSOURI-COLUMBIA VIRGINIA 6RAVITATIONAL COLLISION

• SOURCE TERM MODELS EFFICIENCY MODEL I

h BATTELLE COLUMBUS LABORATORY 0AK RIDGE NATIONAL LABORATORY l

eSOURCE TERM HODELS 7 *HAARM-3 VERIFICATION ANALYSIS I

sREFERENCE CODE DEVELOPMENT

• FAST TESTS eHAARM-3 VERIFICATION TESTS (NSPP)

MOUND LABORATORY eAEROSOL CHEMICAL NRC CHARACTERIZATION b

2r 3

e 3P U

e

~

?

S0lRE TEIN AC00ffLISifENTS e COFLETED DEVEdMEfr OF ON APPARATUS FOR CRI-III AND FASIS IEST (0mD (AucwS DETERMINATim 0F VAPOR YIELDTSTABLISH PRIMARY PARTICLE SIZE) e CmPLETED DEVEUPPENT OF FEL AEROSOL SIMUUWT TEST (FASI) VESSEL (0RNO e CafLETED FIRST VERSIM OF SOURE TEM fbML (0RL U. VA.)

(ALuu PRETEST CALQHTim 0F FAST TESTS)

.Sb W

1

SOURCE TERM

~

FUTURE ErronT (FY-79) e COMPLETE AEROSOL NORMALIZATION TESTS IN CRI-III (ORNL, SANDIA)

I e COMPLETE SERIES OF FUEL VAPORIZATION UNDERWATER TESTS IN FAST (0RNL) 9 COMPLETE ANALYSIS OF FAST UNDERWATER IESTS USING ORNL SOURCE TERM MODEL (0RNL, U. VA.)

AND IHE SIMMER-II CODE (LASL) 4 IMPROVE SOURCE TERM MODELS FOR FAST FUEL VAPORIZATION UNDER SODIUM TESTS (0RNL, U. VA.)

(p

he e

9 9

S3 b

e 8?5l@%

ela a

g i !B 3j e

3 e

I!

s t

3 5

aB E

b\\es 88

-1e e

2 E

E

• f 6l&

b8

'B B

B B

B 3

.5 k5kEEE

[

I

EIE0L TIVNSPORT FunmE EFFmT (FY-79) e COMPLETE HAAIM-3 VERIFICATION PROGRNi AND AluusT PmGRm (BCL, ARSID e INITIATE MIXED AEROSOL TESTS IN NSPP (0fM.)

e CmPLETE CHARACTERIZATIm 0F CHEMICAL REACTIm PmmcrS FRm SODItM-MIXED 0xim INTERACTI m (M0lI E e PLBUSH f!RST VERSIm 0F REFERENCE C0m (BCD e COMPLETE MIXED AEROSOL PROPERW ltASUREMENTS (BCD e DEVEL& IMPROVED COLUSim EFFICIENCY MOEL FOR NON-SPHERICAL PARTICLES (U. Ib.)

S I

~

1 ORL E

TE FAST FACILITY 18 lfE FOR SOURE-TBN ANE #0 SIMR Q]ALIFICATIGl E:GERIfBiTS:

IEutIMICN: A 2' DI#i. BY 6' TALL SWIlN WSSEL G/10 SCALE WR-SIQi T INBR PRII' arf fuiTAIll80.

EERIKiiTS: GN DISASSEELIES T ig S#RES LIER SmilN #0 (NER llATER.

RIESES:

- M BLEBLE FOR%TIQi #010 TION

- REI. VAFOR 01EEATIG{

- REUCOOLAhT IEEFACTIGS

- AERISOL BEHAVIOR Ifi liga BWBLE

- QWiTITf ElfASED T0 LEAD NO QWITITY ETAliED BY SWILH

... ~

4

e e

W"-

\\

,jf

-7..

' tW g

\\,

t sf l ^

"*b 4

l

?-

%eKj f9*T748 KIN

.a v

- g.c F

g

-s h.

n.

s.

b,

[

^

gg[$t?}&9.@Nt l

2,.n E m enwAA

~

_ g ) ~,

k@f3 ~.

k# *[*}[']fyh

!m g

g

-a

= - --

,.n

-"3 g,4 g p _.7 b(

ggyp 2

+

gpy g;

c i

,,wpmay t

. r siiisdBI l 1j I

r

--md_

h 4 o i l

/

P,'

)

I!f l

-.H l

lli Ag -

.g

'N

's

t. J." h $ $ g;4.

1 l

m i'

e l M.k % D.

-e t

J 7

i i

l i

i l'

UtL E

l TIE CRI-III FEILITY IS USED FOR QV IEEGTEIT, SQKE 1BM DERIENIS, SIfffR WALIFICATIG1, #0 MESQ. FidtKlf NASUE-PERS:

I 3

IEIRIPTIGl:

A 0.5 M CWE-ST# FED VESSEL EDJIPED RR METL snEIES.

i EERIPEfIS: GN DISASSEltLIES T LD LMER A V.GM #0 Ill ARHl.

2 f

R H M S:

REL FLASHITE VARR YIELDS PRIIM ibid. SI2E DISTRIHKIGS l

LIQJID FRA6M SI2ES #0 E0 CITIES IEIATIVE 10TIGi-VARR #0 LIWID FPKfEil5

~

9 0

9

. _ _ _3

~..

~

l l l

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Q

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i es.

f,

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l if' -

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h

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+

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)NION

%RBIDE i

""' THE PRIMARY SIZE DISTRIBUT16N OF CDV-PRODUCED AEROSOL WAS'

{

LOG-NORMAL; THIS DISTRIBUTION WAS INSENSITIVE TO THE TEST SAMPLE ENERGY STATE AFTER CDV i

CUMMULATIVE SIZE DISTRIBUTION SIZE DISTRIBUTION FOR FIVE TESTS E

l I

I I

IIIII I I

i i

i a

10 4

- MASS BASIS (ASSUMING A

N

/

~ UNIFORM DENSITY o

A IE

- SPHERICE.

O A

2M

/

~

j.3 0.06 - PARTICLES) 0 i

~

~

^

Z o

b g 1M g

.g 0.02 d

?

i-e t

.m

< 50 NUMERICAL ~

~

e e CDV 21

/

u.

lo---o CDV 29 g

0.01 :

BASIS 2

o m

!=

• AEDC 14 n.

d = 0.014 pm.

' g 20 o---a CDV 16

~

{

g a

}

0.005 9

g 8 = 1.8 CDV 24 a

a z

Ag I

llilli I

i 10 O.01 0.1 1

10 50 90 00 :99.9

, 0.002 0.005 0.01 0.02 0.05 0.1

's

. PERCENTAGE OF TOTAL HAVING LESS THAN AVERAGE DIAMETER IN INTERVAL (p)

STATED DIAMETER g

i l.-

'ea4* -3wG 77-113aa (w Ou u

SUMMARY

OF VAPOR (AEROSOL) YlELD RESULTS. AS A FUNCTION OF SAMPLE ENERGY CONTENT AFTER CDV i

.m i

e Eo a:1 C

[

~

i 9

5 N TED g

'@ UNCERTAfMTY o S10

~

5 g7 0

07 2

ociu w my gh 04 OF o

=

a o

n E

.2 i

I I

g e

Itse 2003 3000 s

l CALCUL.ATED ENERGY INPUT TG PELLETS I

FRQM 298 K (J/G PELLET) 4 l

~

Gil lE TE IEPP IS USED FOR E)PERIFEEAL QRIFICATIGi & TE ARSR IEE0ED AEROSOL BEFAVIOR COE, HMRi-3, USIfE MIXED-SRCIES ABU-SQ.S (REL NO SODIUi-0XIES) llER SEC0ERY GEAINEIT C001-TIQ6:

TPGIPTIal: A 10 FT. DIA9. BY 20 FT. HIGi W.SSEL Eli EWIffED FOR AEEDSO. SRDIES.

EXPERIWIiTS: SIIGI C0fCEE NO MIED AEROSOL TPAIGIBITS.

AEROSOLS PRODUED BY TDIUi POOL ND TRAY FIES, BY RATA-TOR 01 BUR 11tG OF URNIIUi PGER, K0 BY CD&IVRE ELECTRDE BURiiliG OF URN 11Ui RODS.

PmPUR-

- VALIIRTIG1 & CO-AGGLGOATIQ1 ASSLfPTIQ1 NO BEFAVIOR

- QRIFICATIQ1 & fBDSQL IDIl.S

- GRAVITATIQW.SElTLIIE

- PLATE 0K

- WSSEI. SIZE trttt.is

- ATlTIGR AEROSOL IlfhdES

- ONELTIQ1 CURPERS

- TERL GFADIBUS

- trttus T FDISTUE

- VALIDITY T WI.L STIRPG ASSUPTIQi e

IA

- ~ _.

IGP WSSEL PNWEERS ESIR TBfMIUE 423 K QSTO IE513 FIE55GE O.42 JPA GD PSD IMER 3.5 M G0 FD IEIGK 5.49 M G8 FD 3

VIDE 3.3 # G3E5 FT )

nom m 7J # G.9 FT*)

usen.SR9CE E S.9 # OttL6 FT*)

/3 e

9.*

e F

l E

' *EA k

~

1 c e;

}

ww gi 1

M i

8

'R M

E

^C_

f~,

~.' 'E

\\ \\,

L

.33-e:"EL

~

~~~. m' c

.~. :.

^

h

.s,,

_1 'f,,

f,:,,gg~

• i.

_. y,-

4 - y f,.. %

' ' 8 s

..,3,.

geyc-p mi' @g j r-lagg g

t'

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^

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~

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r-or

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N

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Am L 1

' '~ m,_- a s

/4

. ~. -

~. -

s

.s

~

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TABLE I MIXED COMPONENT AEROSOL BEHAVIOR TEST PROGRAM NUMBER EXPERIMENT T.YPE VARIABLES OF i

TESTS 1.

SINGLE COMPONENT (l;a2 x)

TOTAL CONCENTRATION LEVEL..10-120 g/m3 O

g.

2.

SINGLE COMPONENT (U 0 )

TOTAL CONCENTRATION LEVEL.. 10-60 g/m3 38 6**

i 3.

MIXED COMPONENTS -

TOTAL CONCENTRATION LEVEL..20-120 g/m3 8**

l VARYING CONCENTRATION M ASS R ATI O............ 1 :1 LEVEL SIZE DIFFERENTIAL,....... (SOURCE f

AEROSOLS) 4.

MIXED COMPONENTS -

MASS RATIO U O /Na2 x... (2:1), (4:3), (2:3), (1:3)3 3g 0

4 VARYING MASS HATIO U0 CONCENTRATION LEVEL.........

30 g/m 28 SIZE DIFFERENTIAL...... (SOURCE AEROSOLS) 5.

MIXED COMPONENTS -

SIZE DIFFERENTIAL (3 LEVELS) 3 VARYING SIZE

- Na2 x big - U.g 8 small 0

O DIFFERENTIAL

- Na2 x es U O O

3g i,

0

- Na2 x small - U 0 38 big

. CONCENTRATION LEVEL.. 60 g/m3 MASS RATIO........... 1:1 TOTAL 27

• INCLUDES 2 REPLICATION EXPERIMENTS

• • lNCLUDES 1 R'EPLICATION EXPERIMENT

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5 g

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SODIUM y

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• 102 S kg

=

a 103 S kg 5 Z a 104 10 kg T

2

-3 I

I I

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I 10 0

0.5 1.0 1.5 2.0 2.5 3.0 3.5 LOG OF TIME FROM START OF AEROSOL GENERATION (min)

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4 10 40 100 400 1000 TIME (min)

Sodium Oxide Aerosol Concentration.

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RUN 202 5

a RUN 203 2

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I 40 o.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 log TIME FROM START OF AEROSOL GENERATION (min) l i

l i

I 10 40 10 0 400 1000 4000 TIME (min)

Uranium Oxide Aerosol Concentration.

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10 1.0 1.5 2.0 2.5 3.0 3.5 4.o

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LOG,o oF TIME AFTER START OF U og GENERATION (min) 3 l

l 1

l l

40 too 400 1000 4000 TIME (min)

Comparison of Mixed Oxide Aerosol Behavior with Single Component Aerosol Behavior, l6b

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~U-N l

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e NSPP Run 104 HAARM 3 Prediction x Experimental data 15 Sodium burning rate: 53g/ min for 21 min i

-3 10 1

4 10 40 10 0 400 1000 2000 Time, minutes FIGURE 5.

COMPARTSON OF Tile li.\\AR}!-3 CALCULATION RESULT WITil En'ERI)a'stit nin man weme sum nu I9 t

r

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COMPARISON OF AEROSOL BEHAVIOR CODES CALCULATION FEATURE HAA-3 HAARM-2 HAARM-3 AEROSIM PARDISEK0-3B AGGLOMERATION:

BROWNIAN DIFFUSION X

X X

X X

GRAVITATIONAL X

X X

X X

TURBULENT X

SIZE DEPENDENT EFFICIENCY X

X DEPOSITION:

SETTLING X

X X

X X

THERMOPHORESIS X

X X

X BROWNIAN DIFFUSION X

X X

X X

DENSITY CORRECTION FACTOR X

X X

(PARTIALLY)

(PARTIALLY)

DYNAMIC SHAPE FACTOR X

X X

COLLISION CORRECTION FACTOR X

X X

ATTENTUATION FACTOR CALCULATION X

RESTARTING OPTION X

MATERIAL mixture EFFECTS X

UNRESTRICT5D SIZE DISTRIBUTION X

X SPATIAL INHOMOGENEITIES Sg)

MULTIPLE SPECIES R>

. /.

iO' E I

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IE 10' Fg 3

5 W

~

"E e

kl0 E--

=

8 2

e o

M y

xx g

~9 Oo 6, k

2 o

m O

k 4

NSPP Run 103 COMPARISON OF THE HAARM-3 k

~

-HAARM 3 Prediction 9

CALCULATION RESULT WITH Id1 X in-vessel ' Experimental data

~~,-

EXPERIMENTAL DATA FOR NSPP RUN 103 o Ex-vessel.

~

Sodium burning rate: 65g/ min for 13 min.

og_

d=

l l

I I

i 4

10 40 10 0 400 1000 2000 Time, minutes i

E I

I I

I I

I

4. 5

,$ 4

]3 f" N,

2 2 f

I o

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I i

I i

l I

I I

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=

A

-/

x

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N "g id N

N

[

u.

N 8'

0 N

g O g N

g O

6 10 N

o N

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O o

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=

HAARM-3 2

- - - - - H AARM-2 2

e{

HAARM-3 (with reduced Ource O g o.

rote)

- gj O

Experimental Data i*

" I I

I I

I I

O 10 0 200 300 400 500 600 700 Time After Sodium Spill, minutes PREDICTED AND MEASURED RESULTS FOR CSTF RUN AB-1

L;

~

RANKING 0F INDEPENDENT VARIABLES (1)

LEAK RATE (10)

AEROSOL DENSITY (2)

PARTICLE COLLISION EFFICIENCY (-)

(11)

AEROSOL SIZE DISPERSITY (-)

(3)

SOURCE DURATION IlME (12)

PRESSURE (4)

SOURCE AEROSOL SIZE (13)

IEMPERATURE (-)

(5)

SOURCE RATE (14)

AREA 0F VESSEL WALL (-)

(6)

COLLISION SHAPE CORRECTION (15)

PARTICLE SLIP CORRECTION (-)

(7)

TURBULENCE (-)

(16)

TEMPERATURE 6RADIENT (-)

(8)

DYNAMIC SHAPE CORRECTION (17)

DIFFUSION BOUNDARY LAYER THICKNESS (-)

(9)

AREA OF VESSEL FLOOR (-)

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