ML20150B235

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Forwards Summary of 780310 Meeting W/Ornl,Bnwl & Lasl Re Coordinated Program to Evaluate Fuel Cycle Facility Accidents.Proposal Will Be Discussed at 780428 Meeting
ML20150B235
Person / Time
Issue date: 04/19/1978
From: Solberg D
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Bartlett C, Rouse L, Starostecki R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS), NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
NUDOCS 7810300282
Download: ML20150B235 (33)
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wAssisoTou. o. c.nases o,. APR 191978 s,**u THIS DOCUMENT CONTAINS P0OR QUAUTY PAGES MEMORANDUM FOR: Members, Fuel Cyc1'e Facilities tiriuent wn c ru i and Waste Treatment Review Group. FROM: Donald E. Solberg Fuel Cycle Research Branch Division of Safeguards, Fuel Cycle and Environmental Research i .g

SUBJECT:

FUEL CYCLE FACILITIES ACCIDENT RESEARCH On March 10, 1978, we met with personnel from Oak Ridge National Laboratory (E. Frederick) Battelle Pacific Northwest Laboratory (L. Schwendiman, '^ J. Mishima) and Los Alamos Scientific Laboratory (W. Gregory) to discuss a coordinated program in which each laboratory would contribute in their areas of specialization to evaluation of fuel cycle facility accidents. Each laboratory has provided us a draft 189a describing the work they propose to perfom on this project. A copy of each 189a is enclosed for your review. A meeting is scheduled for 8:30 AM on April 28, 1978, in Room 1027 in the Willste Building to discuss these proposals among the review group members with particular emphasis on (a) the ability of the proposed programs to be responsive to NRC needs, (b) the cost-effectiveness of the proposed individual approaches and (c) coordination of the approaches including elimination of unnecessary j overlap. Also, for your information Bill Gregory (LASL) will provide a short presen-tation and will answer any questions regarding his proposal at 1:30 PM on April 27,1978, at the Willste Building in Room 10?7. Interested review group members are invit,ed to attend i: they believe that it would be useful to them. > 1/ d Donald E. Solberg \\ Fuel Cycle Research Branch Division of Safeguards, Fuel Cycle and Environmental Research

Enclosures:

1. ORNL Proposal
2. PNL Proposal
3. LASL Proposal 7810300.:tsy.

s's. ( i Distribution Apg y g 797g C. Bartlett, RES* L. Rouse, NMSS* R. Starostecki, NMSS* ~ J. Ayer, NMSS* A. T. Clark, NMSS* E. Wick, NMSS* P. Loysen 1 ..i r 1 i l

  • Review Group Members r

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OAK RIDGE NATIONAL LABORATORY' FIN /189A NO. 5 ~. - ...Nr,.., UNION C Aft %IDE CORPOR(w7405.end.26 yNg 1,b{]QFg1 .N e NUCL E AR OlVISION ConerwetNo, PROGRAM AND DVDGICT PROPOSAL .... OPl!R ATIN G COST 5. AN D EQUIPMEN T

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NUCLEAR REGULATORY RESEARCH PROGRAM April h, 1978

1. DUOGET ACTIVITY NO.:
2. OFFICE 3, PROJECT TITLE:

Investigation, and Evaluation of Design Basis OR 60-19-30-02-1 Accident Spectrum for Chemical Separation Plants

4. METH00 0F REPORTING:
5. PERSON IN CHARGE:

' PRINCIPAL LNVESTIGATOR(5): =

1. MONTHLY LTR. 0 4. ANNUAL E. J. Frederick H. W. Godbee
2. ' QUARTE RLY 0 5. OTHER:

n O 3. SEMLANNUAL

6. CONTRACTOR:
7. WORKING LOCATION. CITY:
8. STATE:

0 0AK RIDGE N AT. LAB. 0AK RIDGE TENN. ~

9. TYPE:
10. CONTRACT NO.:
11. TASK NO.:

0 i. INDUSTRIAL

4. GOVERNMENT 0 2. ERDA LAB 0 5. OTHER NONPROFIT 0022 N/A 0 3. EDUCATIONAL
12. CONTRACT TERM. BEGIN
13. CONTRACT TERM. END I4. TERMINATION DATE OF FUNDING:

MONTH DAY YEAR MONTH DAY YEAR MONTH DAY YEAR FROM l0171 I0l~ll lTI61 To f3TTl fBTBl n I 91 ratt

15. MAN YEARS FY 1978 FY 19 79 FY 1980 0.8 25 15 Selentific Other Direct Total Direct (Ne Fractions) 0.8 2.5 15, 16.o PROGRAM SUPPORT OOLIGATIONS 40 1h0 100 a) Di,ect solories b) Moierials & Services 6

10 20 c) subcontroces - 100 d) Direct Total Direct Costs h6 150 220 e) Indirect Costs 1h 50 h0 f) Fee Total (In Thousands) 60 200 260 ~ 16.b EQUIPMENT ' one None None Equipment Obligations (in Thousands) Equipment Cost (In Thovsonds) - None None None ut N.s a no e

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u., Investigation enf., valuation of Desit;n }flVITY HO. 60-19-30-02-1 1HLE: Basis Accident Spectrum for Chemical 189 No. Separation Plants T. Cost Schedule: y 3 ~ " Total Prior Fiscal Year Estimated Year 1978 1979 1980 Cost j A. Cost and Obligation Obligation Schedule Task 1 60,000 120,000 25,000 205,0'00 Task 2 80,000 235,000 ; 315,000 Total Operations 60,000 200,000 260,000 520,000 B. Development Schedule (See page 3) 18. Publications : None es <~ 19 Work Scope The objective of this program is to assist the Division of Fuel Cycle and Material Safety of the Nuclear Regulatory Commission in formulating guidelines for the siting of chemical separation plants. ORNL vill prepare an engineering study which assesses the feasibility and cost benefit of reducing the radio-logical dose from maximum credible accidents in a reference chemical separation plant and related fuel storage, vaste solidification, plutonium conversion and facilities to or below a baseline prescribed by the NRC. The study will UF6 include:

1) a review of accident information available for the chemical separa-tion plants and related facilities either proposed or currently designed and/or constructed to establish the continued validity of the conclusions in ORNL kh51,

" Siting of Fuel Reprocessing Plants and Waste Management Facilities"; 2) the development of source terms based on a unit operations approach where applicable, for maximum credible accidents resulting from but not 2imited to natural pheno-mena, criticality, fires, and H2 gas explosions; 3) an evaluation of the affect of process alternatives and alternate fuel cycles on the source terms; h) the calculation of population dose using an accident model, site boundary distances, and population distribution agreed upon by ORNL and NRC; 5) the design of addi-tional plant features and the employment of larger site boundaries to' reduce incrementally the source term available for release to the environment and/or the consequence to the limit of the baseline or belov; and 6) a determination of the incremental cost of each additional plant feature by an AE firm selected by ORNL and approved by the NRC. Credible accidents resulting from acts of sabotage are assumed to be no more severe than the safety-related accidents and vill not be evaluated as part of this program. l ~ l Q .PAGE 2

~.; p r*. ~ I h E-b. m \\z hg NO.17B 189 SUBTASK / MILESTONE SCHEDULE b j g-en tn u FY 78 FY79 FYB0 BEYOND

  • 8 3

3.s "o $ SUBTASK / MILESTONE FY 81 FYB2 FYB3 FYB4 FYB5 t 2 1 3 4 1 2 3 4 1 2 3 4 FY B5 a D c+ A. Development Schedule [Q ooa 1. Task 1. Determination of Accident E[ D

  • c ^ o Consequences a.

Design Basis' Accidents Reviev UV g [ b. ORNL kh51 Reviev 7 ggg U c. Select Design Basic Accidents gw I ' VV d. Develop Accident Source Terms qg e. Affect of alternate processes on I 5E V7 P Accident Source Terms kh ' I I UV f. Calculate Population Dose I I ' I I b U D' g. Final Report n

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g 2. Task 2. Add-on Features Evaluation &e V V .S a. Select and Design Add-on Features @C I I I O V H, b. Develop Source Terms g I I I I UV c. Calculate Population Dose Ii I I I I V d. Add-on Features Cost Estimate I I !!I U V e. Cost Benefit Analysis M2 I D' U I I I I f. Final Report ~ ~ Fs ENE -i: b. a ? 8' i.

h' b E N b liti t i' Investigation and Evaluation of De. ; ACTIVITY NO. 60-19-30-02-1 Bauls Accident S( trum for Chemical )Ho. Separation Plants-20. Relationship to Other Projects: This program would' be related to tiie NRC Programs on the development of ALARA standards for the fuel cycle (h0 10 01 01) and on the safety evaluations of nuclear facilities (h0 10 01 05) and the DOE programs for developing vaste management technology (AG 02 02 03) and for developing LWR and Alternate Fuel reprocessing technology (AG 02 01 2X) and (AG 03 04 05). The Deni n Basia 6 Accident Evaluation Program does,not duplicate the efforts of.these related programs but benefits through the use of the information generated in the related programs. 21. Expected Results in FY 1976: A historical review of chemical separation plant design basis accidents including those addressed in the AGNS FSAR, Exxon PSAR, NFS SAR and ORNL-kh51 vill be completed. 22. Expected Results in FY 1979: Source terms vill be developed for the maximum credible accidents identified for analysis in the study and population doses vill be calculated and compared to the NRC baseline. The affect of process alternatives and alternate fuel cycles on the accident source terms and population doses vill be determined. A study of the cost effectiveness of employing add-on features and larger l site boundaries to reduce accident consequences to below the NRC baseline vill f be initiated. 23 Expected Results in FY 1980: The final report on the Determination of Accident Consequences (Task 1) vill be completed and issued. The cost effectiveness analysis of employing add-on features to reduce acci-dent consequences vill be completed and the preparation of a final report vill be initiated. 2h. Expected Results Beyond FY 1980: The Add-On Features Evaluation report (Task 2) vill be completed and issued. 25 Description, Justification, and Costs of Major Materials, Subcontracts, Computer and Programming, and Other Unusual Significant Cost Items: Costs Estimates Description-and Justification FY 1978 FY 1979 FY 1980 (a) Major Procurement and Fabrication (b) AE Subcontract 100,000 (c) Technical Services (d) Computer Services ,2,000 5,000 5,000 uc N*44 " l

  • PAGE-h

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' ' -itf LE InVc'5tigation and[taluation of Design 6 -1 02-1 Basia Accident Spd. rum for Chemical ("j eto. Sepa.:ation Planto

26. Description, Justification, and Sequential Priority of all Equipment Items:

N/A 27 Utilization of Faci 11tica and Test Insta'11ations: N/A ~ i l t PAGE 5 US"".. v's'>

r i. -( l PIN /tt9a NO.8 (DVANCE COPY 300A01134 enoonAu Ano suocei enore.ai. DATE: NUCLEAR REGULATORY RESEARCH PROGRAM gg, g euoo T aCTwiTv No.:

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3. rnossCT TITLa' HETHODOLOGY AND SUPPORTING INFORMATION FOR ESTIMATING AEROSOL RELEASES OF RADIO-ACTIVE MATERIALS IN ACCII;EHTS ME THOD OF RtrQMTINGs S. FEMSDN IN CH A AGE:

PRINCir AL INVESTIG Af omit): l..C. Schwendiman J. Mishima o i.uoNTnLv s.Tn. o 4. ANNu Ai. G 2 CuAnf 6mLY O S.QTHER O 3 SEMI ANNUAL ~'DHTGtAC'10mi f.WOMKING LOC Ale 0N C47V 5.STATb: p Stiltale Moeno* Lei it.Mituto M4 Mand preAltgen fe<lf sc Nsrth ess Lseesetery

10. CONTR ACT NO.
11. T Asst No.;

. Typt: O t.lNDuSTHIAL C 4.QOV E M N M E NT 8YMC#12 C 3.000 L As. Os.oTHsa NoNenor:T O a.t ouC ATBoNAL

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13. CON ift AC's' TE MM E NDi
14. T ERMIN ATION D ATE OF PuNDING:

Me. De vf. Me. Oey Yia Mw. O GY Tf. FPil F19 GE CIB L3Ih FE8] 05J FW I?l8) 7. p.MANYEAMs FY FY FY

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./- - - ~ U(, NUCLEAR REGULATORY COMMIS! )N SCHEDULE 18s ADVANCE COPY "8-- '***' '" Hethcdology & Supwrting Infor ' ' CICHL AND OPER AU0ml 0FFICE mation for Estimating Aerosol teleases of R.adioedlyg._ Materials in Acciden.ts _. ~17. Cost " arid Development' Schedule: ~~ ~~ ~' ~ ~ ~ A. Cost in Thousands of Dollars

  • Obligation Prior Estimated Schedule Years FY-1978 fY-1979, FY-1980 FY-1981_

Total Costs 70 30 40 Task A 20 70 10 30 130 Task B 20 140 150 150 460 Task C 20 125 100 110 355 Task D 10 76 75 80 240 Task E Total Operation T66 V56 1 31i 376 Tf31i (Includes Equipment)

  • Including equipment costs.

B. Develppment Schedule: l] TASKS AND MILESTONES FY-1978 FY-1979 FY-1980 ~~ ~ ' ' ~ ~ ' " ' ~ ~ ~ ~ ~ JASK A -- Document Eos tula t'ed Design E Basis Accidents for Hixed Oxide Fuel Fabrication facilities." W W WN 7 fonn overview team. y Review SAR's SER's. EIS's accident analyses for M0X facility. 7 Designate model facility. V Draft document. VIssuedocument LA_S,_K 1 -- Document "Sup)orting infor-mation for Evaluation of.)otential Source Terms from Non-Nuclear Initiated l Accidents in Fuel Cycle facilities". W WW Compile published information. Draft document. Tissuedocument. IASK C -- Experirnental program-aerosols ~ W__9W@cWdM3/AE genarated under accident conditions. ~ ~ Y Establish experimental protocol.' y Design and fabricate experimental equipment and procedures for first series. i.

j U.S.Nd.EARREGULATORYCOMMISSION I .o..... ,v.,,,...v.. ......n....v. 5CHEDULE 189 i ADVANCE COPY 3 _) ""*" ""

  • Methodology and Supportin Infonnation for Estimating Airborne Re ease ' I mcm.a.o neceiarious arrics J

of.Radioactin. Mater.ia) irtAccidants-TASKS AND MILESTONES FY-1978 FY-197g FY-l'980 l TbComplete experiments, ycDraftdocumentcoveringexperiments. ydissue document. l Q D2 sign and fabricate experimental equ pment and procedures for second ser es. 7,Completeexperiments Draft document covering experiments. Issue document. TASK gn behaherimental pr$ gram-time de-g pg 7,g, g,, j - Ex pencfe ior of conta ned aerosols. y Determine experimental matrix.. ll Design and fabricate experimental 7,equpmentandproceduresforfirst ser es ' 73 Complete experiments. f 7c Draft document, Issue document. j Design and fabricate experimental i equ pment and procedures for second Ser es yCompleteexperiments. 1 i \\/c Draf t document. Tolssuedocument. Ed TASK E -- Experimental program-leak rate 6'f accident generated aerosols from con-WWaWh 3 WMYR..i tainment. 7 Detennine experimental matrix. j Q, Design and fabricate experimental l equipment and procedures for 1st series. Complete experiments.

l Draft document.

ygIssuedocument. J..

/e n, .r, Uh. NUCLEAR REGULATORY COPHIS. N -..... ~.......,.................. "ADVA'NCE COPY 5CHEDULE 189

      • =.4 esiis' viv6=~hthodology & Supwrlisl0 Infor-:

cie.ca c or..anons emc8 - mation for Estimating Aerosol telua6us of .Redjotetive Mattriali_in Assidents, TASKS AND MILESTONES FY-1978 FY-1979 FY-1980 Q,equipmentandproceduresfor2ndDesign and fabricate experimental series. Gb Complete experiments. 7cDraftdocument'. Ydssuedocument. i 18. Publ ica tions : This is a new program, hence, there have been no reports or publications in this project. In Appendix A is a list of relevant reports written by those who could participate in this study. 19. ,Pu,,rpo m Need and Scope: Safety analysis reports and environmental impact statements must address the po-tential consequences of postulated accidents in or involving the facility in question. Airborne release is conmonly the dominant pathway to man, and it is thus necessary to determine a "sourcs term" (the quantity of radioactive released as a function of time) based upon an accident scenario. The scenario i,i a sequence of largely inadvertent events which lead to various thermal and mechai:: ical stresses on equipment and materials involved. The scenarios frequently in volve the energetic breaching of primary and secondary containers through natura,: or man-precipitated events. Typical events range from simply spilling the mater p 1al (free-fall through air) to more energet.ic injections of the material into air due to the. rupture of the container by impact, crushing or penetration, to air-borne release due to fire, explosion, earthquakes, tornadoes, etc. For a rationa,i assessment of the event, the scenario should address the questions: How much hazardous material is placed in jeopardy by the event? [ e What is the. probability of the event occurring? e What are the characteristics and amount of hazardous material potentially [ e airborne as a result of the event? E What are the' characteristics and amount of hazardous material released and e -carried by the wind from the facility. L What is the disposition of the material carried downwini? At the present time, considerable difficulty is faced in making such rational assessments, largely because information permitting such analysis is scattered throughout the literature in many diver',e areas or is lacking altogether. Acci-dent or failure probability data is scattered throughout many governmental agencies, industrial and engineering associations and laboratories. Somestudicsp eis n =

y U.. NUCLEAR REGULATORY C06941SS. A ......o., -,,.........,............... 5CHEDULE 189 ADVANCE COPY 5 Methodology & Supporting i

      • 'v"

cecata o oesamoas omes Information for Estimating Airborne Release of Radioactive Material in Acciden L __ i available on the release of radioactive materi u der thennal and aerodynamic stress (see references in the Appendix). Data lacking on the fractional release from free-falling liquid or powders; powders or liquids forcibly ejected from con ' tainers ruptured by jmpact. crushing or puncture; radioactive materials adhering to structural surfaces and filters dislodged by vibration (earthquakes, etc.) or i rupture (rapid depressurization); powders entrained from small mounds due to wind action, etc. From limiting conditions such as the maximum airborne concentra-tions of aerosols which can be generated at various air velocities are ill de-fined. t Pacific Northwest Laboratory proposes research which will assist materially in assessing accident consequences, in particular those in which radioactive mater-ials may become airborne. The program will embrace major elements or tasks, as described in the following sections. 4 lasM -- Scenarios for mixed oxide fuel fabrication plants. Task A will be accomplished by defining and cataloging the design basis accidents (08A) for mixed oxide fuel fabrication facilities. Only non-i criticality process-related accidents and natural phenomena will be consid-I ered. Other fuel cycle facilities will be considered by other contractors r (Fuel reprocessing facilities by Oak Ridge National Laboratory, etc.) by j arrangement with the U.S. Nuclear Regulatory Comission. In this task we would review safety reports on existing and contem) lated mixed oxide fuel t fabrication plants to define circumstances under witch accidents could be initiated and to establish the course of the event. Attention would be given to the nature of the toxic materials involved, the stresses imposed in the 3 event. the enclosure integrity, room configurations, ventilation systems response, etc. A principal o dective would be to identify the range of variables which must be bounded in developing the infonnation needed for " objective" analysis of accident consequences. Output of this task would be useful in the following tasks as well since the search for infonnation on mixed oxide fuel plant accidents would be added to the information bank to be developed in Task B. Task B -- Literature review of published information on the airborne release of contained radioactive materials under accident conditions. The objective will be to identify accident situations in SAR's, EIS's, decom-missioning studies, etc., and data available to evaluate such situations. This will provide input to the experimental program and act as a data bank of information for individuals responsible for acc dent evaluation. In this literature review and assessment we would develop the description of postu-lated accident scenrios with enough detail to set boundaries on the max-imum and minimum involvement of radioactive materials, their range of dis-persal qualities and disposition in the system, containment and enclosure configurations, ventilation system. response, and other considerations which l This review will influence the course and consequences of the accident. M .....w "~

U.s(.4UCLEAR REGULATORY 'COMMISSI[ } ~ ....,... ~ ,w...,...... ADVANCE COPY 5CHEDULE 189 ,.. 6 ~ Uhi)dology and Supporting i M ca.ess, virus cic.n.ano ersuvione arric" information for Estimating Airborne Release of Radioactive Mat _eria1 jn Accidents I would be-aimed at establishing the " envelope" of the source term. This infor ; mation would help determine the most productive experimental studies and place bounds on the range of posssible variables. An attendant and equally important element of task B will be the collection and organization of information on the generation and behavior of powders and liquids under various stresses imposed in accidents. Data on dispersability of powders and liquids, stability of aerosols under various assumptions, depo- ! sition, re-entrainment, release under thermal stresses and other particle and liquid properties and response characteristics would be gathered with an ex-tensive bibliography provided. This is considered an important output of Test '

8. since this compilation would provide an important aid in accident conse-quence assessment.

Task 8 would also identify areas for which data were lack-ing for objective accident assessment and help in the design of experimental studies to fill in where data were lacking. Tasks C, D, and E involve experiments to determine aerosol behavior in strest situation which have been identified or which will better identified in Tasks A and B. i in order to reduce the scope of the experimental portions, the prox > sed pro-gram will not attempt to simulate any > articular accident (where tie situs-l tions are of ten complex and dynamic), aut will focus upon situations an aero-sol generation mechanisms which are present in many accident situations and for which fractional releases are not available. Even these simpler situa-tions are relatively complex and the study is not intended to be parametric. Rather, a reasonable upper and lower bound of conditions will be evaluated with as many intermediate points as deemed desirable. To help focus and prioritize the work the investigators will draw on their experience in inden. tifying data currently lacking and the com lexity of the experiments required' to obtain the data (design and fabrication procurement of equipment, measure-ment of results, etc.). In order to have a comprehensive program, the experi-mental matrix should be based upon a review of the situation covered in SAR's and the data used to evaluate these situations. Because of the extra effort expense and risks of using plutonium and other highly radioactive gamma and beta emitters, simulated, readily measured material s will be used, in most experiments. A fine, well-characterized . uranium dioxide powder is currently available and will be used to represent heavy metal. oxides. Concentrated uranyl nitrate solution will be used to simulate heavy metal solutions.- Analytical services to measure these mater-1als (dioctyl phthalate, uranine, zinc sulfide, etc.) having other character-istics that have been used in other investigations of aerosc>1 behavior will also be used as applicable. Materials having specific characteristics re-quired to evaluate certain mechanisms or situations will be identified as .the program unfolds. Trace or limited quantities of radionuclides may be used in a few experiments if the chemical nature of the compound plays a sig-: nificant role in the aerosol generation / behavior / release process. Tasks C,'D, and E are as follows: l u seu ese u.n i

e,, -,.., U( NUCLEAR REGULATORY C0&NIST 'N ...in... w.v.,.c..... ...een v...... SCHEDULE 189

        • __7_.
  • aense nr's Metfiodol'ogi'and Supporting me awo orsaaviews ornos Information for Estimating Airborne Release '

,.of_._R_adioa_ctive Mate _ rial in Accidents. "~ Task,,C--Investigationofaerololgenerationinaccidentscenarios. This task is directed toward evaluating the airborne release of particles and : liquids, during stresses which may be imposed in an accident. The elements l of this task are the following. I i e Design of Experiments. Objec tive : Design experiments and procedures to obtain meaningful re-i sults, set boundaries, etc. Subtask will continue throughout most of program with major commitment i of effort in early stages. ~, Design, fabrication./ procurement, and assembly of experimental apparatus. o Objective: Provide functional apparatus for complex experimental setups and measurements. (This function is not anticipated for initial simpler experiments.) Aerosols generated by the free fall of liquids and solids. l e I Objective : Quantity and size distribution of liquids and solids made i alrE5rsi during spillages. Effects of height, material characteristic, air velocity to be deter-mined. Aerosols generated by aerodynamic stress. e Quantity and size distribution of aerosol generated by air DJAjective: Sasiliig~over pools of liquid and shallow deposits and piles of powder o. 1omogeneous and heterogeneous surfaces. Aerosolization of deposited >l powders will use both vertical and horizontal surfaces, with and withou:.. j 'I vibration. Aerosols generated by rapid depressurization/ explosions. e Aerosols generated by rupture of glass / sheet metal containers by impact,:l e crush, and puncture Aero' sol generated by subdivision -- Breakup of glass, cement, bitumen. pellets by crush. impact, penetration fire, etc. Aerosol generation experiments will be performed in a schedule of priorities set in Tasks A, and B. Task D -- Investigation of aerosol behavior following release in constrainec.. ,i limited volumes. L Time dependent behavior of contained aerosols. ji e Objectiv Depletion of puff 'and continuously released aerosols in 1Tmi ted _.t:lume. vo .i ou... n.,s

/ ( ) ... r.. u.vir..,... r.a.. u v. ...r. / SCHEDULE 189 ADVANCE COPY ... _ s no... Hens Metho'd51ogy anTSupporting cic,.ca o oesamous errics Information for Estimating Airborne Release of Radioactive Material in Accidents. i Measurements as functior, particle characteristics, aerodynamic environemnt, j containment volume, etc. Maximum airborne concentration as a function of f important variables. Task E -- Investigation of dynamic exchange of air and particles from a failed compartment. Determine time dependent concentrations within the i enclosure and the rate of aerosol and air released. l Objective: Experiments to be conducted to show time dependent concen-tVatTons in an enclosure as a function of particle characteristics, the air exchange and aerodynamic properties, (including heated plumes), leak rates, and size of openings). Evaluation of depletion mechanisms. e e Model development. i Methodology for using the infonnation. e NOTE: Los Alamos Scientific Laboratory is currently involved in a program with ob.jectives which parallel those of Tasks C and D. LASL's program investigates i the behavior of ventilation systems under energetic flow regimes (tornadoes, ex-plosions, etc.) and includes the modeling of flow fields and particle transport by these flow fields in the facility. Discussions with personnel involved with these programs indicates no serious overlap. The flow capability of the Pr4L wind tunnel requires upgrading to attain a desirable degree of overlap to providc' cross-comparison capabilities with LASL experiments of such items as aerodynamic entrainment. The LASL experiments on the time dependent behavior of contained i aerosols and their modeling efforts center around large volumes (i.e., a large room). PNL's study would center around glovebox size volumes and smaller. 20. R_ elated, Studies: Studies related to the proposed work and those which would benefit from the work ' < proposed are: consequences of severe natural phenomena on existing plutonium facilities e in the United States. Site decontamination and decommissioning studies for DOE. Plutonium hakage. from failed shipping containers. e Safety analysts studies in licensing facilities using radioactive mater-o ' t al s. Study of improved contamination control in enclosures through new concepts e L in ventilation. 21. Techni, cal Accomp1,tshments in F1, cal Ye'ar 1978: { s The principal technical accomplishments ancitipated for the program are shown in u.iw ein ni [ ' ~ '

x U. 5( '.4UCLE AR REG.UL AT.ORY C.OM41 S.S.l. ADVANCE COPY 5CHEDULE 189 i 9 Ja&E Tiivi.s-Rithod611igy'and Supporting nicut.no oesnatio=> or rics Information for Estimating Airborne Releasc of Radioactive Material in Accidents .... - - ~ ~ ~ Item 17 and are as follows: Formation of a study team on design basis accidents in mixed oxide fuel e plants and collection of accident scenarios. Experiment design and initial experiments on aerosol generation. e Design of wind tunnel modification to increase flow capabilities to approx-l imately 60 mph. Specification for laser spectrometer system to study the time dependent be-e havior of aerosols in gloveboxes. 22. Expected Results in FY-1979: i Task A -- Document " Postulated Design Basis Accidents for Mixed Oxide Fuel Fabrication Facilities". Task 8 -- Compilation of published " source term" data. Task C -- !ssue topical reprots on first series of experiments on aerosols. Task D -- Issue draft report on time dependent behavior of accident gener-i ated aerosols in work enclosures. Task E -- Release rate of aerosols from faulted gloveboxes determined for several scenarios. ll 23. , Expected R_esults in FY-1980: Task B -- Compile additional published data and update document as required. Task C -- Draf t report on second series of experiments and complete third. 3 ? Task D -- Develop or verify model to predict time dependent behavior of i aerosols in glovebox. Design and fabricate equipment to measure time dependent behavior of aerosols in smaller volume (Air Trans-j port containers). 24. Expected Result) Beyond BMdget Year; i Task 8 -- Keep abreast of " source term" data and provide data bank for i " source term" information. Task C -- Continue experimental program to define aerosols generated under ! accident conditions until experimental matrix is complete. Task D -- Determine time dependent. behavior of accident generated aerosols in limited volumes and. *in conjunction with LASL, determine scal-ing factor, if any. nasa < ess es.w (

a U.( NUCLEAR REGULATORY COMMISE 1 ......... ~.........,... .. ~..... 10 2DVANCE COPY -. ~ rae,sev vm.= Methodology and Supporting Infortnation for Estimating Airborne Release j ,c,a...,uavians or rica of Radioactin BateritLin Accidents. Task E -- Determine leak rate of aerosols from faulted containers and in conjunction with LASL, determine scaling factor. if any. i, l; 25. Description and Justification of Ma,jor Materials,____ Subcontract _ Items and Other_ j U7iuTuil Tj l ih n'i f i c a n t"Co s t' I t ems. ' ' " ~ ~ t i-it is anticipated that off-site experts Will prepare overviews of the stresses -l imposed by severe natural phenomena earthquakes tornadoes and hi h winds the responses of structural materials an equipment do stresses, and ssibly fres l and explosions for Task A. Accumulation of documents and articleu for Tasks A and 8 may represent a significant cost. ll 26. Descript_ ion, Justification and Sequential,,Pr_iority of al1. Equipment: ,j FY-1979 $25,000 P r i or i ty 1 -- S pec i al E qu i pnent.................................. Special equipment will be needed to simulate crushing, punctur-ing or propelling containers to simulate various stresses which might be imposed. This equipment cannot be specified in detail at this time, but would likely be mechanical devices selected- { to produce the needed stresses. Priority 2 -- New air blower for wind tunnel and installation costs, enlarge llEPA filter banks, and continuous $30,0; flow measurements.................................. The range and versatility of the wind tunnel and large aerosol chamber for part of this work would be upgraded with a larger fan to increase velocity in the test section. This upgrading r il is needed to help establish trace aerosol behavior under a wide [ range of air flows. I, Priority 3 -- Instruments which permit improved definition of real time flow fields and particles will be $50,0 2 acquired........................................... A laser spectrometer to measure the real time behavior of con-tained aerosols is required to define the time dependent [ behavior of aerosols in gloveboxes. [ } FY-1980 $25,0r P r i or i ty 1 -- S pec i al E qu i pmen t.................................. i Special equipnent will be needed to simulate crushing, punctur-ing or propelling containers to simulate various stresses which might be imposed. This equipment.cannot be specified in detail at this time, but would likely be' mechanical devices selected to b produce the needed } tress. u sou.ess s,.w \\

t u.s. n; lear Raquiatory conmission J ........., u.......................... SCHEDULE 189 _ 11 - __ l l . ADVANCE COPY ,..u , um MethodoT6g~y and '5Iipporting Information for Estimating Airborne Release i,. a.e airua noas o* ncs of Radioactive Material in Accidents - APPENDIX A, RELEVANT REPORTS AND PUBLICATIONS SY PNL AUTH WOULD BE CONTRIBUTING TO THE STUDY A Review of Research on Plutonium Release Durina O HW-836687Ceneril Electric HAPD, RichTind, VA~{X~uiust,~T95TJ'. ~ J. Mishima. fires. Release from the lgnited Metal, J. Mishima. Plutonium Release Studies. I.~ ~ ~~~ BNWL-205, Battelle-Nort.hwest, Richland, Wh~~{0echinfeT,~196!i). Release f_romig,nited B_ulk Metallic-J. Mishima. Plutonium Release Studies. Pieces _, BNkL-357, Battelle-Northwest, Richlan_d, WA (November L.C. Schwendiman and C.A. Radasch. Plutonium Release Studies, J. Mishima, lease f rom Plutonium Bearing Powders, BRWLT786,~TaTteTle Ill. Re Richland, WA (July,1968). fractional _ Airborne Release of Uranium _(Repre-J. Mishima and L.C. Schwendiman,sent.ing (Plutonium) During the Bu BNWL-1730, Bit' tells-NorthJest, Richland, WA (Apri1~,1973),. Plutonium Release Studies IV. Fraci a J. Mishima, L.C. Schwendiman, C. A. Radasch. '~ ~ fTT tional Release from Heating ' Plutonium Nitrate So1ut' ions in a'f o < ng BNWL-931','Battille-Northwesti'RichWnT WA~lNo~esber,19687.~ ~~ Some Ex_perimental Measurements of kir - J. Mishima,(and L.C. Schwendiman. Representing Plutonium) in'Tr ~ ~ ~ ~ " ~ ~ ~ it't eTE-No r thJe~s t, R i c h l aii'd7W A l A u g u s t, 1 W3). Uranium B Airborne Release of Particles "it L.C. Schwendiman, J. Mishima, and C.A. Radasch.Over_he ~ Satte11e-Northwest, RTciiland, WA (AuDust,1968). ~ Incidents. The Airborne Release of Plutonium..During Overheatin9 BNWL-SA-2695, Battelle-Northwest,' Richla'nd,' 4A' (Novemtier,"If59) J. Mishima. The fractional Airborne Re-Interim Reaort: lease of Dissolved Radioactive Materials Surin_g the Combustion 'of 30 Percent J. Mishima and L.C. Schwendinan. IrbNormal' Butyl Phosphatfin' A' Kerosin~e lEpf Diiution BNWL-B-874. Richland, ~ ~ WA (July, 1973). Radiciodine, BNWL-319, Battelle-Northwest, Ric J. Mishima. The R,elease of "Kr from Water -- An Interim R,epor.t,,, BNWL-CC-2395, Bat.telle-Northwest, Richia J. Hishima, t..C. Schwendiman. J. Mishima, Potential Airborne Relesse of Surface (December,1}?3). n. %....

/ lbkd /Nv7//dz [a ) ADVANCE COPY ~ ~ ~ ~ non c Gina Methodo' logy a'n7 57ppo~rIing- ~ ~ ~ ~

.c,.t a-o ore m a no
o.,les Information for Estimating Airborne Release of Radioactive Materi,_al in Accidents.

L.C. Schwendiman, J. Mishima, and 6.E. St.egen. Airborne Plutonium Release Postu-lated for Serious Accidents in a Consrerical ScaTe'~Re_ cycle Mixed OxTile Fuel Iabrlcat1,on Plan,t, BNWL-19?2'~EiatTJeTle Northwes(, Richland~9A-(To be ~ issued). J. Mishima. " Data tiseful 'in the Examination of Airborne Plutonium from Postulated Accident Situations" Appendix C of Considerations in the Assessment of the i et all, BNWL-1607), Battelle. Northwest, RTchland, WA" (June, l'971).(J.CS Consegunnces of E f fluents from Mixed Oxide TueT TibrTcat fon~Mant J.M. Selby, et al. Technological Consid.erations in Emergency jnst.rungp.tation Pr_e-paredne , Phase 118 - Emergency Radiological and Meteoro1 ical Instrumen-tation 1 r Mixed Oxide Fuel f abrica.tio'n f acilitTes,lRQL l 2 Batteih-~~~ ~ ~ Northwest, Richland, WA lApril 1973). S.V. Anderson, et al. Technological Considerations in Emergency Instrumentation Preparedness. Phasi~1f 'C- ' Emergency' RadiologiFal Instrumentitl6n ToTT~iT-Fabrication Reprocessing facilitifs, BNWL-1857. Battelle-Northwest, RMfand, WA T Au'g~us~t 1976). ~~ J. Mishima. " fractional Airborne Release of Plutonium Under Shipping Accident Conditions" in,Proceedip,3s of 4th International _Sympos. lum on. Packaging a_rtd Iransportation of Rad'ioactive Materials, CONF-740901 U.S. A.E.C. (1974). tainers in Transport Packaging,for Rad,f oactive Materi,a,h (ged Shipping Con-J, Mishima. " Potential Aerosol Generation Mechanisms from Dama IAEA Seminar. Vienna 23-27 August, 1976). (..C. Schwendiman and 5.L. Sutter. Transport of Particles Through Gas Leaks -- A ~ Review, 8NWL-2218, Bat t elle-Northwest. Rich 1' aid 7 W(~ January,1971). L.C. Sr.hwendiman. Supporting informat.3nn for the Estimation of Plutonium 0xide ~ "~ l eak Rates Thro' ugh Very Sma_11 Appertures. UNWL'-2T~9W7 Ba tte11c-Northwest", Richland, WA (January 1977). Rq 1976 to oiiitiin L. port -- Oc tober 1, i SMpHng Con-Quarter 1v Pro L.C. Schwendiman, et al. De_c e!nbu r 31,.1976.. A_ 5t'udj o f Pl.ift'g re s s1.de i.eak ~BHis ~Ffon t ainerg UNWL-2260-1, Ba t telle-fdorthwes t, Richland, WA (to be issued). L.C. Schwendiman, et al. Quarterly Report -- January 1,to March 31, 1977. Study. of Plutonium Oxide i eak Rat es f rom Shipping Containers _, BNWL-2250-2, Batte11e Northwest, Richland, WA

  • (to be issued).

J. Mishima, t.C. Schwendiman, and J. A. Ayers, llSNRC Study of Analysis of the Ef-f eet of Nat ural Pl enryena tJynr! Existing Plutonium fabrication facilities, (in prugress). 4 64 4 004 Olb 14 16 e ' l

i_ _. '1 ^ M, I.Ast. sp-F sNil29s h0a v ( y PitoanA:. )C4T PROPO5t L LA S L # N.. _. _ _l Nt1 CLEAR RHGU ' RtiSEARCil PROGR AM oxT:n April 17, 19L : 1 " rT l p -..=.u-. A. 4...y - u ~.. 4 94 __2

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2. I Lsuo s . l ; ) J,, ; Allaung INVESTIGATION OF ACCl M.NT-!NDUCED FLOW AND MATERIAL dpc rai TRAN5180RI IN NUCl. CAR FACILITILS (AID) di RHO.) O~. AS/Oct i sNGt

5. FdeuGN IN Cit AilGE:

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m. f.lON ill DAY YEAH S10 NTH DAY YEAH F.1 D N T H D AY YE;.H b3 k.M lE b3 b) bM 3?.) O3 [b ) TO ~ ..- FY 'l978 FY 19/9 Fy 1930 f.1 AN YE AHs 0.5 3.0 3.5 $:istitific _O. I.. _ __. _ _ _1 3.. ._. _7 _5-'~ _ ._O_ t_ta.r oi.t ect Tot 41 Djreet (No Fr acticrul 0.6 4.0 5.0 ~'~~~~~ ~ ~ ~~"~" " ~ ~ a r.1cor sa.t sono.troat.icAnads 17.9 123 162 .1 o;.u s4:4,i,, 49 1./ 36 ./ 6 '. in t.i n.,isi r. smi.n . _.._!4 0 _.. a s.a.um ga. .s (II U t*60 f ().f f.* $ 1.cai nis co cau. 19.6 209 286 10.4 7I 94 ,1 s..a,. : n.u:, . I

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S;hedule lil9 ) cheddle I 1/. Cost and Oe' -e A. Cost ant gatlun Schedule Total Fiscal Year Estimated 19 /fl'~f9,)flfiti _Cnst ($/1000) 1. rlow Dynamics 10 100 130 240 11. H.iterial Trarisport 10 100 130 240 lit. Re-in tra lenstant /Dopos i tion 10 tl0 120 210 30 280 380 5690 18. Publications H. H. Anitrae, R. A. Hartin, W. S. Gregory, " Analysis of Huclear f acilities for lornada Induced flovi and Haterial l'ransport," bos Alarnos Scientific 1.aboratory, report in preparation. 4 0 4 4 ~ - ^ - - - - - - -

.] , April 19,1978 { E W. S'.' Grcig'ory 1 Schedule 189 E ( t' ) t i ' i, i { 't l j 17.8. Developina hedu1e

  • i MAJOR TASKSfji.UlH ASK_S.

FY.1978 FY 1979 P/ ~ l l FLOW DYNAMICS i i A. Literature & inodel review J -] ,-] 8. Report explosion snodel work C. 1-dhoensional fire-induced finh model I, D. 2-dimensional velocity distribution model 3 a E. Couple 1- & 2-diniensional inodels i f-F. Add internal obstacles to P-d hnensional niodel i; G. Integra te explosion models j l 11. Integrate exporbnesital llEPA filter data j I 1. 3-diniensional velocity distribution roodel i j 11. HAICHIAL THANSP0Hi j A. Ef tera ture & inndel review I i i l l B. Identify significant paranieters l;; --j l C. 1-diniensional model/ tornado 1 0. 1-d hnuns tonal miodel/ firo ll -{ 1 E. 1-d finensiona l inodel/ explosion fl F. 2-diniens ional uindel developinant G. 3-d inien s io 141 model devulopnient. I 11. Couple surface flux model/2-0 modal 1. Integrate llCPA filter material release data l l l Hl:-ENIllAlflMEN T/DLPOSI T10t1 i A. Literature survey B. Assessment of experimental data p C. Characterize plant conditions 1 D. Re-entrainment/ current information model ] ] C. Computerite calculations j [ F. ' Fill gaps in existing experimental data G. OcVelop surface flux mndel it. Experimnnts for threshold speed, su, pension. Ioading conditions, etc. I., Experiments with pulsed flow, l flow reversal, finw angularity J. Experiments with shock waves r

i..

( ' Apri1 19, 1978 . eire ory S.:hedule fl9 19. Scope The fluclear Regulatory Cnirmission's (N!tC) responsibilities for profuction of tlio general pistilic frain nuclear ef fects include assuring that nuclear facilities aie adaquately dusigned for any possible acclel. nt t:ontlit ion that could result -in Accident ra.11oactivo snatnelal release to the environtaunt. conditions, as discussed here, are considernd to be those events that'could be man-causild (explosions, ffre) or that result f roni adverse natural phenovna (carthquake, tornado). 1he poss lhle env t ronment al cons igo.'ncess of thoser accidants impact on proposed system designs, and tiieir effects must be addressed by 1icense applicants. The applicants' analysets are It is subsequently rovinued anri evaluated liy the HitC. difficult, if not tidpossible, for the NRC to perform safety evaluations of either new or exist ing f acility.insigns without J analytical techniques anil supportive experimental dat.a on poss ible acciolent scanarios. Also, the degrou of conservatism is tilf ficult to d.itermine without a or risk assessment syst em.it it ' appro ich I'or _ust hn.it inq rea list ic accident constquences. f environment il convntuences of an acc iditait l As.os i.n nt of ' lt imit ely involves r alculat ion ol' atm.npherle disper:; ion ulth u ra. ior t ivo do. ige e'.t im.)I os f or t h.i surenion.iing popol.:I ion. l~lne siopo of Ihi, invest iq tt. ion u t i I nol in. lo lo ionslitsratinn f. ol' at.w.phor ic h.ur. port, I,u t will he l h ill. 'I t o pre.f ic t ion j 1 1 l-

/ \\

1. *

( W. S. rre.jory -5 April 19, 1978 Schenule 199 of accident-induced material movemant within the interior of a nuclear facility. The final product of the investigation will he techniques that perm t better estimates of release or source term characterist.ics at a plant's atmospheric boundaries. The proposed program is divided into t.bree ma.ior research These arn 1) accident dolinuation and survey, 2) areas. internal source term characterization and release, anti 3) intuced flow and material transport. Investigation in therse three areas can ho pursued simultaneously,provided tasks in each area are coordinated to achlove overall program objectivas. To carry out its portion of tint lovest igat ion, we propose that the Los Alamos Scientific l.aboratory (LASL) undertake responsibility for research area (3) as outlined above. This entails developmont at techniques to cairnlate the indoced flow and matorial transport from an internal accident source to a plant 's afiriospheric boundaries. Work assignments to separate orgini/ations for each major area will requirn a central managemant to integrate the prograin tasks and minimize areas of unnecessary overlap., We therefora suggest that LASt. assume lead laboratory responsibility for the overall program. This is s,uggested for two reasons: First, work in area (3) requires considerable intoraction with area (?) to insure that proper paramaters anii required data are generated for input into the

~ e s t-( L S. Gregory - f, - April 19, 1978 'chedule 189 calculational tec.hniques of area (3). $ccondly, since IASL's unrk in area (3) will provide the end product from the proposed program, we will to a large drpree be assuming uitImate responsilillity f or the progrem's success. In this capacity LASL wnuld not dictate prngram criteria to other organ 17ations, but art only to ailvise NRC on matters of conrdinat ton or integration that are essent tal f or program success, The end prodnct of the proposed program will lie analytical tools anil techniques tlint enn be used by the HRC staf f in their saf ety analyses. As noted above, t hese tools will result f rom LASI.'s wnrk in area (3). Appropriate analytical rinricis in flow i,1yn am i c e., material transport, and enti alnment/ deposit ion will be developed. These analyttr.nl models will take the form of usabic tiipit al ( nmput er programs I allni erf esper ially f or the NRC's computing capabillties. The analytion1 model development will he supporled by experimental work, par t (cularly in the area of re-entrainment/depositlon. Also, ongoing NRC-sponsoreal experimental work at LASL will also be integrateil into the model development areas. PO. Relat lonship to oil er pro,iet is predict ions of tornado indurett transient finw rate., preuvre ~ (.hanges, and spat ial velocity dist ritiot inns within roome, and duc ts can be olit aintil us ing existing umputer codes developed at the Los Alamns Scientific laboratory. The codes ~ t ~

W. S. Gregory - 7.. April 19,1978 ."icherlule 109 are TVElli (pressure t, flows) and SOLA-lCE (velocity distributinns). Codes such as these are neederi to providt! ] inputs nf fInw rele onel e.urf are velocity to any model nf re-ent rainment usert t o estimat r> source terms. An experiment al program is underway to obtain supportive tlata on ventilat inn system rnmponent response to high iInw rates. Testing of a modr1 ventilation system is planned to check t he t rule T Vl Hl. In a:Idit ion, lif pA filters are being tested to determine their structural integrity and filtration effettiveness under tornado ronditions. An explosion code is being developnd to prerfIct venillation l syntcan response in shor k overpressore Inarfings, f xpor iment al wnrk using a 34-in diamoter shock iu!.e to generate f ast pr r'ssure tranc.ient s will support the-explor.lon tode development.. Pl. [xpe( 1 ed Rec ni t e. in f Y 1970 i As an initial task the f1RC computing r.apability will be ouest.ed to filent if y rest rict ions and par t ir.ulai r equir ement s. The results will influente the character and type of mndels developer!. The work.ncoded t o pretfitt induced f low and rnatorial transport under acc ident confli t lon<. (an lie suhdtvided into three ma, lor areas of inndel development. These principal invest innt ive areas are in 1) flow tlynamire., ?) mator ial transport, and 3) re-ent ra lnment/ deposit ton. The last coerter of fY 1978 ulli he devoted to implementing iho inIt1al stages of Ihe propused prngram. Specific tasks in cat.h major area during TY 1978 are:

- - J' } 5.Greonry -R-April It), 1978 'l ' :Imdule 109 i e I. f Inw flynomics A. Review literature regarding model development that has particular applicability for acc ident-induced f lows. ) fl. Out line one-climensional mndel development needs based on task A. Requirement s to describe flow for tornado, explosinn, and fire have airca'ly been ident if ietl. C. Keep flRC cognizant of tornadn and explosion mottel tievelopmt nt progr oms that are f untled by of her agencies. D. Istablish the er.sent in1 element <. necessary to dt u rlhe fire-induceti flow (heat transf er-linuyancy). Revicev lit erature and availabic mntiels that can c. be used to calculate two-and three-climensinnal velnc Ity dist rlhut tons. In particular, iA$L's 501.A-ICE (.omputer corte will be examined for this appilcatinn. 11. Mater tal Transport A. Perform a literature review of analytical techniques that have been used to describe innt er ial t ransport. In particular, review the exist ing marfels llAA-3 and SSM-b developed at Rockwell Inter. national. I

~ d ,~ ( W. $. Gregory April 19. 1978 Schedule 1l19 I ~ II. Irfentify significent parannters that tmest be rnodeled such as plate not and agginneratinti d phrnremena. l C. f stablish the type of snoi els that need t i development for one, two, or three-climensional eppilt.ation anil cletermine how they will interact. III. Re-entrainment/ Deposition A. Survey r xisting literat ure f or suit able analyt Ircs1 tools to calculate re-entrainment anel deposition. B. Assess present ly availabic experiment al riat a anel stmi-empirital re-eniralnnent equatInns. C. Charat ter 17e expetiett plant part iculates, sur f atos, anil surf ace loadings. Par (icular empha*.is will be ploccil on venttiotion pathways such as <lut.twnrk. D. [xatnine th" f easibility of developing analytical musicls for inovement anr1 pnss ihic re-enti alnment. of surf ar.c mat er ial une!cr aerodytiamic sterss. e 4m e a

i J ( i W. S. Gregory April 19, 1078 ' chedu l e - 109 / ?.7. Expected Results in TY 1979 Thi' f ollowing t asks in the ma.ior areas of flow dyncmics, 7 material transport, and re-entrainmcet/depor.ition will he unclertaken in FY 1979. 1. rInw Dynamics A. Begin develope nt of a nne-dimensional mortel that w111 destribe ilow dynamics assoclated with fire. fl. Report progree. on cyplosion code developnent. De9 n development nf a two-dimensinnal mortel that 1 C. will t air.ulate transient velocity siistributions. if f ccts of compressibility will be included, but internal obstar.1es will not be Inc ludert. D. fxamine feasilillity of coupling one-anel two-tilmenr. inna i i inw dynciiii >....!.1;. f. Couple the two. dimensional model with the existing tornado model,1VIfil, if feasibility is shown in task D. ]1. Hat erial.Tr ansport A. Development of a one-dImrensinnal matorial This tran'. port nrulel will be undertal;cn. ttanspori ninctel will ar.c.cpt t he convr'ri ive cf f er ts av.nc iated with and der (ved f rom the inrnarfo e ntle, I VElfi. 3

  • k,

.s I. 'f.

5. Gre nry Apr11 19, 1978 Whedule 89 R.

Development of a two-dimensional matertal transport model will be undertaken. This ~ transport model will ac cept two-dimensional ] convective effects, allow deposition and input from a surface flux, and provide boundary conditions for the one-dimensional modol. C. fear,ibility of coupling the one-and j two-dimene,lonal mat erial transport models will be er.ami t ted. D. The one-and twn-ilimensional tunic 1s will bc cnupled if fensibility is shown i n T a e.h C. . Ill. f!c-ent r ainment /Depos i t ion A. provide inf ormat ion and dat a to eupport J development of mat.erlal tranc. port models, fl. lindel re-entralnm"nt and deposition hae,vd on currently available Ittcas and perform preliminary calculetiens of material release that tiract:ct realist it plant condit ions. C. Initiate development of a inethod that will implement or couple calc ulations in task B f or the materini ttansport mndels. D. Uht nin experinn nt al dat a f or small heavy materini t 0 imprnvc the e.emi-e npir ten 1' equal tone. in lash it. I:. Initiate develoirnent of a material surf ace flux ~ inodel that will provide input informat lon for the one-and two-i mensional material transport li models. i

.y ( t ., S. Greoory .jp. April 19, 1978 a' a.bettu1e 109 ? t 71.Expec ted Results in i Y 1980 j. 1. Flow Dynamir.s - In F Y 10PD, the one-dimensional model that simutales f tre-induced flow will be cornpletert. Also, the coupling of this mnriel with a two-dimensional model vill I I be examiner!. As in prior years, the !!RC will be inf ormed l on progress in developnent of an cy.plosion model. Poriions of ihe expinsinn moilt 1, esper.Ially snodels f or explosive deflagrations, will tie integrated into this Work wIth t wn-dimen<.1onal mortels f or dr't ailed pr09 ram. 4 veltuity distrihotions will be er. tended io include i internal obst ac tes in the f Inw f ield, t, 11. Mat t r ial 1ransport - The onn-dimensional material transpori mn lel suit abic f or tnrnado finw parameters wi11 he complet ed anel ext en<fod to inclurie f ire-Indtn.est finw. The two-allmensional mat er ial-transport inodel will also be complet eri in IY 19R0. This mndel will aucpt material f rom a sur f are f lu.x and be extended to accept a material i source at an internal location within a room or cell. 111. Re-entrainment / Deposit ion - l~yper luents will be conttur ted in tietermine mater tal threshnid speeds, suspension, and i i dnposit ion f lor.cs f or realist ic material charac t erist ics. Realist it surf ace, f Inu cnndit ions, and varyinu deurecs of surf ar e loatlino will also be examined. The results of these experiment s will be used to t herk ex ist inq equat torr. that have been developed,primarily to predict l re-ent.rainment for soll and sand. If the latter equations prove to be unsat isf actory, we will develop new cardLlemfkr Beral emint Ions f or our surf ace flux mnde1. a

s *

l. S.-Grenory

( 13 April 19, 1978 ' therfule ign I M. Expected Results Drynnd Budpet Year Invest igat ions beyond the budget year would allow extension of ' flow-dynamics and material tr ansport modeling to three-nimensional models. It may not be pnssthin to morici three-dimensional phenomena in a twn-dimensional sense. Therofnre, we believe that f on tomo cases a tbree-rllmensinnal snodel would be necessary to atturately represent the flow and concentration fields. Other modeling consirlerations would include (nupling of the re-entrainment surface flux motlel to the two-dimensional matei tal transport mnrici. Adtlit innal results from the expInsion modri develepnent will have to be integrated into the program at they beto9e availabic. Also, by this' time, experimental dat a f rom of her programs should hetome avaliabic and wi11 he inrorporated intn the analyt iral mortels. Other areas of investigation in tbe re-entralnment/ dern<,lt inn area thnt have a disect bearing on an estimate of source terms also lie beyond the scope of effort within the budget year. Ihnse incliule the cf f cc ts on suspension of pulsed flow, finw angolarity with respect to the dnposited substrate, flow reversal, and floir separatinn. These erfects are all likely to occur in vent 11at inn systems under tornado condtt ions and may be dependent on room anel duct penmatrles. An assessinent nf the relat Ive imporiante or ihese erf er ts unuld seem desirabic. In addit ion, we propot.c t o invest igate the of f ec t on re-ent rainment of shock movement over a part iculate . bed. l L D

~ d' r..,. i 5, Grepnry \\. 14 April 19, 197fl ' t herfule 189 b. Dec.cript ion and Just ificatinn of Ma,ior Materials, Subtoniraci ltems nori Other linusual Significant Cost items flo signifI<. ant cost items in this cat.npory. ate foreseen for FY 1978. In FY 1979 and beyond, major material needs will be necessary to support expt rimental work in the re-entrainment erva. P.asic support ive e xperiment al dat a to fill gaps in the literature in addition to experiment al t ests, to support analytiral model development are necessary. We anticipate that most of t he test. wnrk can tie accomplished using exist ing test facilities operated by LJiSt for the llRC. Ma.ior material Items will lie ilinse nes.essary in art omplish these modif it.allons. 55. Description,.lustif icat ien, and Sequnnt ial Priority of all equipment A majority of the equipmrnt netos'.nry to support ihe experimental test ing in t his program is avail.'bic f rom previous ~ fiRC spone.cred Programs. Several addit ional items are needed, hunaver. These equipment items locitnic hot wire anemo:neters f oi measurement of vriet ity prof fles anel torbulent Intensitles in boundary layers, llist ellaneous elect ron ic equip nent sin.h a*. di ital voltmeters, X-Y plotters, t ape recorder <., and a 9 correlater/ spectrum amplifier will also be oct.essary. a e W.w}}

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