ML19345B569
| ML19345B569 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1980 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1762, NUDOCS 8012020082 | |
| Download: ML19345B569 (11) | |
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MINUTES OF THE 1
ADVANCED REACTOR SUBC0fdITTEE JUNE 30, 1930 LOSANGELES,CiLIFORNIA The ACRS Advanced Reactor Subcor:rnittee met on June 30, 1980 to discuss the NRC's sponsored research on advanced reactors. The emphasis was on the NRC sponsored research on advai.ced reactors at the Sandia and Los Alamos Labora-tories. The notice of this meeting was published in the Federal Register of June 13, 1930 and June 26, 1980. Copies of these notices are included as Attachment A.
The schedule for this meeting is included as Attachment B and a list of attendees is includel as Attachment C.
The complete set of materials provided to the Subcommittee is in the ACRS Files. No oral statements were given by members of the pu511c nor were there any requests for time to give oral statements. No written statements were submitted. The ACRS members in attendance were Dr. M. Carbon Subcommittee Chairman, Dr. W. Xerr, Dr. J. C. Mark, Dr. M. Plesset, and Dr. P. Shewmon. The ACRS consultants in attendance were Dr. I. Catton, and Dr. S. Siegel. The Designated Federal Employee was Dr. R. Savio of the ACRS Staff.
INTRODUCTION - R. Smith, LASL I
Dr. Kelber indicated that the budget status was unchanged since the June 13, 1980 Advanced Reactor Subcocnittee meeting. Dr. Kelber noted that NRC planning for ~
the FY 82 budget was consistent with the OMS guidance for the advanced reactors research program (funding for $5 M in FY 81 with program termination taking place in FY 81). Dr. Kelber indicated that he believed that the advanced reactors research program should be retained. He noted that the program was established and was productive. He noted that DOE has a massive LMFBR program an'd that the NRC effort is required to help DOE to focus on issues of potential concern to.,
licensing. The termination of the program with restart at a later time would h5eahighcostintermsofthelossofprogranresources.
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Advanced Reactors June 30, 1980 SIMMER DEVELOPMEf4T STATUS - J. Scott and R. Smith, LASL
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Mr. Scott and Mr. Smith surrarized the status of the SIMMER code development.
The code is directed at transition phase analysis. The SIMMER code is currently being used to analyze core disassembly dynamics, recriticality in bottled-up-core configurations, and molten pool core dynamics. Future development goals are the developmentofa3-Dcapabilityandtheincorporationanddevelopmentofadhanced fluid dynamics models. The code is currently in use in the United States and in Europe and Japan. The current work is directed toward the study of the CRSR homogeneous core and the 1000 MWe Conceptual Design Study heterogenecus core.
Keyissuesaretheccherenceoffuelmotionandthedehelopmentofabottled-up-core configuration. The analysis to date indicates that for a bottled-up-core configuration recriticalities would occur. The initial transient is characterized hy an initial low rate of coherence, with the involvement of more fuel leading to a coherence of fuel motion and to larger reactivity ramp rates.
Improvements in freezing models.will be essential.
ANALYSIS OF ANL CRITICAL EXPERIMENTS A series of critical experiments were performed in ZPR-9 for transition-phase, distorted-core geometries. Comparison calculations have been made between the Mcnte Carlo analysis originally performed and SIMMER neutronics calculations.
Within the SIMMER neutronics models a capability exists for preparing a trans-port versus diffusion method, heterogeneous versus homogeneous treatment, isotopic versus anisotropic treatment, and the effect of the detail in the energy grouping up to fifty energy groups. It was concluded that the diffusion theory was inadequate for predicting fuel-motion reactivity changes in the presence of large near-voided reg' ions, that the transport theory under predicts fuel-motionoutofthecoreandcherpredictsfuel-motionintothecore,andthatthe uncertainties in the prediction of neut.ron leakage appear to be controlling in the prediction of experimental reactiiity changes. The SIMMER transport mcdels were able to adequately predict the reactivity changes associated with the distorted-core geometries studies.
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'AdhancedReactors June 30, 1980 SIMMER VERIFICATION OF FLUID DYNAMICS EXPERIMENTS - J.. Scott Mr. Scott sumarized the SRI and Purdue similar verification experiments. The SRI experiment is a small-scale, two-dimensional gas expansion in a liquid pool experiment. The Purdue experiments with small-scale nitrogen expansion and water flashing experiments..The SIMMER fluid dynamics models were found to adequately predict the results of the experiments in the 1-100 atmosphere pressure range. Model improvements were needed in the 1000-2000 atmosphere range. Some improhement can be obtained by decreasing a mode size and time steps but with a significant cost penalty on computer time. The effect of structures on system kinetic energy is well predicted by SIMMER within the range explored by these experiments.
SIMMER ANALYSIS OF STEAM EXPLOSIONS - W. Bohl, LASL The SIMMER code" was used in the analysis of steam explosions in the Zion / Indian Point studies. Mr. Bohl sumarized the results of this analysis. The analysis treatedthebehahiorofthemoltencorewithin apressurehessel. The analysis predicted upward kinetic energies in the 1000-2000 MJ range. The two-dimensional aspects of the analysis were found to strongly influence the analysis of the dynamic loading of the pressure vessel.
It was concluded that an improved
. analysis should better consider the core-melt-sequence incoherence in the fuel dynamics and an improhed treatment of the structural accomodation of the pres--
sure pulse. Failureofthelowerdesselappearstobemorelikelythanupper head failure.
SUMMARY
OF SANDIA PROGRAMS - J. Walker, Sandia Mr. Walker summarized the programs at the Sandia Laboratory. The major facilities at Sandia are the ACRR pulse reactor and the melt facilities. The programs on thesefacilitiesaresupportedbyanadhanceddataacquisitiondehelopmentpro-The testing in the ACRR is directed towards the understanding'of prompt gram.
burst energetics and fuel disruption, the dehelopment of an effectihe equation-of-state, and the understanding of. debris bed and molten pool heat transfer.
Work in the melt / sodium pour facilities is directed towards the understanding of molten core / concrete and sodium / concrete behavior. Standard construction concretes and barrier materials (Mg0 and high alumina content cements) are 4
being studied. Work in ACPR on carbide fuel testing is being sponsored under a U.S.-CABRI exchange agreement.
It is expected that exchange agreements
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lAdhancedReactors June 30, 1980
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between NRC and EURATOM and Japan will be in place and core-debris-coolability testing will be conducted under this exchange agreement.
ACCIDENT del,1NEATION STUDY - M. Clauser, Sandia I
Mr. Clauser described the accident delineation work being conducted at Sandia.-
This work was initially' directed toward the study of the CRBR reactor. Phase I (fault tree construction) is completed and a report has been issued. The Phase II (fault tree qualification) is currently underway. Work has recently been initiated which is directed tcward the study of the 1000 MWe Conceptual Design Study reactor.
ACCIDENT ENERGETICS - P. Pickard and W. Camp, Sandia Mr.~Pickard and Mr. Camp discussed the accidents energetics program being carried t
on at Sandia. "The work is directed towards the understanding of the fuel dynamics associated with the initial phase of the accident, the work potential associated with the fuel melt, and the behavior of the core in the transition phase. Fuel failure modes, the work potential associated with the fuel coolant interation, i
and the potential for the existence of a bottled-up-core are the key questions.
A series of in-pile tests are being run in the ACRR. The tests'run to date are capsule tests. Funding permitting, an in-pile flowing sodium loop will be developed. Out-of-pile experiments are being performed in which fuel freezing and ablation phenome a are being studied. Theresultstodatehaheindicated apotentialforenergeticfuel/coolantinteractionandfuelbehahiorinthe upper and lower blanket regions which could lead to the formulation of a bottled-up-core configuration.
CORE DEBRIS BEHAVIOR - R. Coats, Sandia Mr. Coats summarized the core debris behahior work being conducted at the Sandia t.aboratory. The D-series tests in ACRR'will be directed toward the Onderstand-ingofcoredebrisbehahior. Four tests have been perfonned to date. A total of sixteen tests, running through 1984, are planned. The MP-series out-of-pile experiments wil1.be conducted in support of the in-pile D-series work.
Four experiments have been completed to date and three additional experiments are planned:for the future. Small scale fragmentation experiments have also been conducted. The work to date indicates that debris beds have a high potential for heat transfer and the establishment of equilibrium bed configu-rations..
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AdhancedReactors June 30, 1980 MOLTEN CORE / SODIUM CONTAINMENT TECHNOLOGY - D. Powers, Sandia Mr. Powers summarized the molten / sodium concrete. interaction work being conducted at Sandia. The work is directed toward the characterization of core melt / sodium containment interactions. Erosion rates and chemical reaction characteristics are being studied. Concrete and liner materials are being studied in the sodium concrete interaction experiments, with construction concrete, high alumina con-tent cenent, and Mg0 are being studied in molten core concrete interaction work.
Larger scale molten core pours (210 Kilograms) will be performed in the future.
The work performed to date has indicated that sodium concrete interactions within ranges of interest are not reaction-product limited and that barrier materials such as alumina cement and Mg0 have high design potential.
CONTAIN CODE STATUS - M. Clauser, Sandia Mr. Clauser described the CONTAIN code development. The CONTAIN code is the integrated reactor containment systems code. The effort at present is orientated toward the study of containments for sodium-cooled reactors. The code, however, has a high potential for use in the analysis of LWR containment systems. The CONTAIN code involving state-of-the-art models is currently operational and the dehelopmentofadvancedcodemodelsisproceeding. The CONTAIN code was used in the Zion / Indian Point studies.
NOTE: For additional details, a complete transcript of the meeting is available in the NRC Public Document Room,1717 H Street, N. W., Washington,0C 20555 or from Alderson Reporting Company, Inc., 300 7th Street, S.W.,
Reporters Buidling, Washington, D.C. 20024,(202/554-2345).
Teders! Register / Vcl. 45. No.11e / Friday. June 13.1980 / N: tic s 40264 Steven N. Anastasion, or CDR Carl A.
NATIONAL FOUNDATION ON THE ke NATIONAL ADVISORY COMMITTEE Moritz. Staff Dtrector for the Operations ARTS AND THE HUMANITIES by CN OCEANS AND ATMOSPHERE and Services Subgroup. The mailing Dence Panet (Dence Touring Program 1
independent Area Task Force address is: NACOA. 3300 Whatehaven and Long Tecm Engagements);
Subgroup on Ocean Operations and Street. NW. (Suite 438. Page Buildmg
- 1). Washington. DC 20:35. The Meeting telephone number is ( 02) 653-7818-Pursuant to secdon 10(a)(:) of the fp Servicea; Meeting Pursuant to Section 10(a)( ). of the Federal Advisory Committee /.ct (Pub, go Federal Advisory Committee Act.5 Dated. lune 11.tesa L 92-463), as amended, notice is hereby U.S C. ( App.1976). notice is hereby Steveo N. Anastasloa.
given that a meeting of the Dance Panel givsn that the Independent Area Task T.ncurne Duveror.
(Dance Touring Program a Long Term b*
Force Subgroup on Ocean Operations ps x.s a rw ss os w Engagements) to the National Council and Services of the National Advisory an.u.o come asie.ius on the Arts mil be held }uly 16.1980 Af:
Committee on Oceans and Atmosphere from 900 am-700 pa July 17,1960 g
from 9 00 a.m.-7:00 p.m.: and July 18.
(NACOA) will meet on Tuesday and NAT10NAL AERONAUTICS AND 1980 from 920 a.m.-7:00 pm in Room 1
Wednesday. }une 17-18.1980. The SPACE ACMINISTRATION 1422. Columbia Plaza Office Complex.
Ex Committee will meet in Room B-100.
P:ge Building Number 1. 2001 Wisconsin 1880t
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Tuesday session w 11 convene at 9 00 Notice of Intent To Grant Excfusive Panel review, discus sion. evaluation.
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ca and Wednesday's at p.00 a.m. Both Patent Ucense and recommendation on applications for will be open to the public.The Monday Notice is henby given that financial assistance under the National f
session will adiourn at 5:00 pa and the consideration is being given to the grant Foundation on the Arts and the S,.
session onTuesday will adjourn at 3:00 to Virgmia Research Institute. Inc of Humanities Act of 1965, as amended.
pa Arlington Virginia.of a hmited.
Including discussion ofinformation NACOA has initiated a study to exclusive revocable license to practics given in confidence to the agency by 6[
formulate nabonal goals and objecuves the invention desenbed in U.S. Patent grant applicants. In accordance with the for the oceans in the decade of the No. 4.118.014 for "An Improved determination of the Chairman
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1980's and beyond. To support the Vehicularimpact Absorption System" published in the Federal Register u.
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conduct of this study. the Secretary of issued October 3.1978. to the February 13.1980, these sessions will be I
Commerce has established an Administrator of the National closed to the pub!ic pursuant to the Independent Area Task Force (IATT) for Aer nautics and Space Admimatration subsections (c)(4),(6) and 9(b) of rev NACOA. Ite IATF. with its subgroups.
on behalf of the United States of section 552b of Title 5. United States bu:
will be responsible for the preparation America.The proposed exclusive Code.
rev of prelimmary recommendations in the hcense will be for a limited numbe.r of Fur *herinfomation with reference ta thh area of marine transportation, energy.
years and will contain appropriate terms this meeting can be obtained from Mr.
ocean operations and services, waste and conditions to be negotiated,in John H. Clark. Advisory Committee eng manage =ent and fs.lluton, fishenes,accordance with the NASA Patent Management Officer. National me-o and ocean minera lacensing Regulatiens.14 CFR 1245.2 as Endomnent for the Arts. Washington.
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This initial meeting of the IATF revised April 1.1972. NASA will D.C. 20306, or call (:02} 634-4070 hel.
Subgroup on Ocean Operations and neg tiate the final terms and conditions M Cd.
ma-toi Services will address the follomng and grant the exclusive license unless, hr4WMWh
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- 2. Development of work plan.
Contributions Board. NASA.
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- 3. Assignment ofindividual tasks and Washington. DC 0546, receives In wit ~
an2.ses coon rear-ews areas of responsibility.
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- 4. Sc.hedu.e of future meetings.
with supporting documentatfort (i) a 463
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scheduling this meetmg prior to the Proposed exc!usive license:(ii) an Advisory Committee on Reactor the
- er!cr NACOA meeting are the reasons apphcation for a nonexclusive license Safeguards. Subcommittee on to p
- '- e. rt public notice. Persons under such invedon,in accordance Advanced Reactors; Weeting t.e dr a to attend will be admitted to the
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%e ACRS Subcommittee on or is Advanced Reactors will hold a meeting l to b estent seating is available. Persons es nt wishing to make formal statements hkely to bring the invention to practical on June 30.1980 at the Best Westeru hu shou d notify the Chairperson, of the application within a reasonable period, Airport Park Hotel. 600 Avenue of Ch' Sabgroup on Ocean Operations and ne Board wiu nyiew au wntres Champions. Inglewood. CA. Notice of brvW r. Dr. Robert M. White, in responses to the Notice and then this meeting was pubhshed May 15.
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adv u ce of the meeting The recommend to the Administrator 19ea obt.
Chairperson retains the pre ogstive to whether to grant the exclusive license.
in accordance with the procedures Ih' crose limits on the duration of oral Dated: June eassa outline in the Federal Register on catemsats and discussions. Written S.Nei1 H - L n October 1.1979, (44 FR 56408). oral or Ee; l statements.nay be submitted before or Ceneralcounsel wntten statemerts may be presented by la after eech session.
members of the public, recordings wdl A.1<iti.nal informstion concerning pu on. an.csie rsw ium ad =l be permitted only during those portions
= = coon n oewe this c eeting may be obtained through of the meeting when a transcript is beics tne Ned.OA hecutive Director.Mr.
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'4026S Federal Regist:r / Vcl. 45. No. Its / Friday. Jun213.19e0 / N: tic;s kept. and questions may be asked only Dated: !une 10.1;80.
regarding the matters covered by tus a
notice, should submit such views or se must l Elk..
by members of the Subcommittee.its requests for additionalinformation to consultants. and Staff. Persons desirmg Secretory of rA, commission, the U.S. Nuclear Regulatory to make oral statements should notify grao= a w anr w s.tumam Commission. Washington. D.C. 20555.
the Designated Federal Employee as far mumo caos runwus Attention: Chief. Utihty Finance Branch.
m advance es practicable so that of N clear Reactor Regulation.on sppropriate arrangements can be made
% g g,4, g g; IY to allow the necessary time during the Deted at Bethesda.Md this 1sth day of mestmg for such statements.
Misslaalppi Powee & Ught Co, et al.;
May 1980 De ager.de for subject meeting shall Mectlpt of Additional Ar:Utrust For the Nuclear Regulatory Commission.
Information: Time for Submisalon of be as foUows:
Ylews on Antitrust Matters A. Schwencer.
Actas chief. ucensing Bmach No.1 Dvision Mondoy, June 30,1980-a:30 o.v ;mtil
- lh#'^888-theconc sion ofbusmess pubbshed in the issue of May 30. Isso. It is ya om.swa m rw s.a w a mamal De Subcommittee may meet in reprinted at the request of the Nuclear name coot rens.aws Regulatory Commassion, Executive Session, with any ofits Mississippi Power and Ught, pursuant consultants who may be present, to to Section 103 of the Atomic Energy Act NUCLEAR SAFETY CVERSIGHT explore and exchange their preliminary ofl954, as amended. has filed COMMITTEE opmions regarding matters which should Informatica concerning proposed be considered durmg the meetmg.
additional ownership of the Grand Gulf information-Gathering Tour At the condusion of the Executive Nuclear Station. Unita 1 and 2. The He Chairman of the Nudear Session. the Subcommittee will hear current holders of the construction Oversight Safety Committee is preuntations by and hold discussions permits are Mississippi Power and ught announcing that the Committee will wita representatives of the NRC Staff.
Company and Maddle South Energy. Inc.
perncipate in an infomatin-gathering tear consultants and other interested ne application proposes to add South tour of two facilities according to the persons to continue its review of NRC Mississippi Electric Power Association foHowing agenda:
fundmg and program direction or as co-owner;it contains infomation fune 30. Isa0.-The Institute of program termination as appropriate.
requested by the At'eney General for Nuclear Power Operations. Atfants.GA.
De ACRS is required by Section 5 of the purpose of performing an antitrust fulv f.1880.-ne Savannah River the1978 NRC Authorizat2on Act to review of the applicatiota as ad forthin Nuclear Power Installation. Aiken. SC.
teview the NRC research program and to CR 50. Appendix !.
De tour, e r.lusively for Committee budget and to report the results of the Construction of the Grand Gulf members and staff, will consist of review to Congress. In order to perform Nac! ear Station. Units 1 and 2. two infomation-gathering actMues only this review, the ARCS must be able to boiling water reactors, was authorized and therefore is not considered a engsge in frank discussions with on September 4.1974.This construction.
meeting under the provisions of the members of the NRC Staff and such is currently underway at the applicants Federal Adviso Committee Act.
alte in Caibome County, Mississippi.
Inquiries sho d be directed to Mr.
discussions would not be possible if
%e original application was dated Andrew Federbar (802/255-4331).
held in public sessions. In addition, it November 17.1972: the related Notice of Dennas E M any be necessary for the Subcommittee Receipt of Apphcation fw Constmetim bhold one or more closed sessions for emits and FacWty Ucenseeh fa krAgAW h Wn the purpose of explonng matters Submission of Views on Antitrust June 10. tesa involving proprietary information. I have Matters was initially published in the yao.sunnerwwuame.at determined, therefore,in accordance Federal Registae on December a.1972 (37 same coor sess.v.a with Subsection 10(d) of the Federal FR 25964).De Notice Receipt of Advisory Committee Act (Pub. L 93-Application for Facility Operating CFFICE OF MANAGEMENT AND 463). that, should such messions be Ucenses; Notice of Availability of required,it is oecessary to close Applicants' Environmental Report: the SUDGET portions of this meeting to prevent Notice of Consideration ofIssuance of Project To Omkp the Ureform frus' ration of the above stated aspect of Facility Operating Ucer ses and Notice Procurement System Proposal the ACRS' statutory responsibilities and of Opportunity for Hearing was b protect proprietary information. See 5 published in the Federal Register on July Aotwcy: Office of Federal Procurement USC. 552b(c)(9)(B) and 552b(c)(4).
28.1978 (43 FR 32903).
Policy. Office of Management and A copy of the above documents are Budget.
Further Information regarding topics available for public examination and agno,c Notice of $eetings open to the to be discussed. wksther the meeting copying for a fee at the Commission's publis.
has been cance!Ied or rescheduled, the Public Document Room.1717 H Street.
Otairman's ruling on requests for the NW, Washington. D.C. 20555 and at the suvu(av: Pub. I. 96-43. the Office of opportunity to present oral statements Caibome County Chancery Cerk's FedertProcurement Policy Act and the time silotted therefor can be Office. Caiborne County Courthouse.
Amendments of 1979 (41 U.S.C. 401 et.
obtained by a prepaid telephone call to Port Gibson.Mississippt.
seql provides that the Administrator the cognizant Designated Federal Any person who wishes to have his for Federal Procurement Policy shall Employee. Dr. Richard Savio (telephone views on the antitrust matters with dev'elop and submit to the Congress, by 202/643-32871 between 8:15 a.m. and respect to South Mississippi Electric October 1980 a proposal for a uniform 540 p.m EDT.
Power Association presented to the procurement system including uniform Attorney General for consideration or policies, regulations, procedures, and s
who desires additionalinformation forms.
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The timing and format of this notice received for review since the last Int have been changed to make the (49 tt S C.1903(a;l:).1%)
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form:
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Points receiving coupon orders withm.
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Draft Agenda e
LASt Presentation to the ACRS WG-6 on June 30,1980 in l
Los Angeles B
8:30 - 8:50 Introduction Scott 8:50 - 9:50 Transition Phase Scott / Smith 9:50 - 10:10 Analysis of ANL Smith Critical Experiments 10:10 - 10:30 Break 10:30 - 11:00 Analysis of Fluid -
Scott Dynamics Experiments 11:00 - 11:30 Analysis of Steam Bohl Explosions 11:30 - 11:50 Near and Longer Term Scott / Smith Improvements 1:00 - 1:15 Introduction - Sar.dia Prog.
Walker 1:15 - 1:45 Accident Delineation Clauser 1:45 - 2:45 Accident Energetics Pickard & Camp 2:45 - 3:00 Break 3:00 - 3:45 Molten Core /Na Containmeat Powers Technology 3:45 - 4:30 CONTAIN Code Status Clauser 4:30 - 4:45 Elevated Temperature Walker Design 4:45 - 5:00 End of Formal Presentation y.
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Draft Agenda - ARSR Presentation to the ACRS. WG-6 on July 9,1980 8:30 - 8:45 Introduction NRC 8:45 - 9:15 Reactor Safety Modeling and Hummel Assessment (ANL)
'9:15 - 9:45 3-0 Code Development (ANL)
Sha 9:45 - 10:30 SSC Code Development and Guppy Testing (BNL) 10:30 - 10:45 Break 10:45 - 11:05 Therma 1 hydraulic LMFBR Safety Ginsburg Experiments (BNL) 11:05 - 11:25 Aerosol Measurements and Gieseke Modeling for Fast Reactor Safety (BCL) 11:25 - 12:20 Aerosol Release and Transport Kress from LMFBR Fuel (ORNL) 4 4
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