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Responds to FOIA request.App F documents available in PDR. App G documents encl & being placed in PDR.

Accession Number: ML20207A169

Date Released: Tuesday, October 29, 2024

Package Contents

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• ML20207A164 - Responds to FOIA request.App F documents available in PDR. App G documents encl & being placed in PDR. (18 page(s), 10/30/1986)
• ML20207A573 - "Corium Coolant Mixing (Task A)," monthly progress rept for Jan 1986. (6 page(s), 2/14/1986)
• ML20207A177 - "Fuel-Coolant Interaction Program," monthly progress rept for Nov-Dec 1985. (4 page(s), 12/16/1985)
• ML20207A552 - "Reactor Safety Research Program," monthly cost-status rept for Feb 1986. (2 page(s), 3/17/1986)
• ML20207A242 - Submits opinion re necessity of large scale 1.000 kg experiments.Conversion ratio of fraction of available chemical energy converted to mechanical energy is single parameter that characterizes all experiments. (2 page(s), 9/23/1985)
• ML20207A471 - Informs that author feels multiple explosions through premature triggering most likely scenario in meltdown accident.One-dimensional fuel-coolant model has greatest possibility of accurately depicting key fuel-coolant mix. (2 page(s), 6/18/1986)
• ML20207A247 - Forwards second draft of tentative experimental proposal, "Phenomenological Studies of Large-Scale Steam Explosion Efficiencies." Constraint experiments more closely simulate conditions during accidents & considered first priority. (15 page(s), 9/13/1985)
• ML20207A362 - "Corium Coolant Mixing (Task A)," monthly progress rept for Jul 1986. (5 page(s), 8/12/1986)
• ML20207A407 - Forwards pages to Part IV of paper entitled, "On Probabilistic Aspects of Steam Explosion Induced Containment Failure." (12 page(s), 7/16/1986)
• ML20207A496 - Monthly progress rept & financial accounting for NRC Research Order 60-86-001,FIN A-2260,Task B,for Apr 1986. (3 page(s), 6/6/1986)
• ML20207A479 - "Reactor Safety Research Program," monthly cost-status rept for May 1986. (2 page(s), 6/16/1986)
• ML20207A217 - "On Probabilistic Aspects of Alpha-Mode Containment Failure: Part I." (74 page(s), 11/30/1985)
• ML20207A260 - "Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program,June-Jul 1985." (46 page(s), 7/31/1986)
• ML20207A211 - Requests permission to use COREXIT facility in experiments to investigate effects of multiple melt jets & water depth on corium breakup & mixing,quench rate,hydrogen generation & debris characteristics. (8 page(s), 11/7/1985)
• ML20207A432 - Provides progress of fuel-coolant interaction program. Investigation re importance of structures to mixing of molten fuel w/water & influence of structures on interaction characteristics of FCIs begun during FY86. (3 page(s), 6/30/1986)
• ML20207A517 - Forwards std order for DOE work for FINs A-2016-6,A-2232-6 & A-2260-6. (6 page(s), 4/30/1986)
• ML20207A253 - "Fuel-Coolant Interaction Program," monthly rept for Aug 1985. (4 page(s), 9/6/1985)
• ML20207A422 - "Reactor Safety Research Program," monthly cost-status rept for June 1986. (2 page(s), 7/9/1986)
• ML20207A550 - "Corium Coolant Mixing (Task A)," monthly progress rept for Feb 1986. (4 page(s), 3/18/1986)
• ML20207A483 - Forwards tentative experimental schedule for statified contact mode tests. (7 page(s), 6/16/1986)
• ML20207A196 - Forwards draft "Investigation of Steam Explosion Loadings W/ SIMMER-II," for review.Meeting suggested for 860115 to discuss results. (52 page(s), 11/18/1985)
• ML20207A315 - "Fuel-Coolant Interaction Program," monthly rept for May-Jul 1985. (5 page(s), 7/31/1985)
• ML20207A418 - Forwards Parts III & IV of five papers on alpha-failure,for review.W/o encls. (1 page(s), 7/11/1986)
• ML20207A412 - Forwards remaining three parts of presentation on containment failure probability due to steam explosions.W/o encls. (1 page(s), 7/15/1986)
• ML20207A223 - Informs of quantification of new mitigating mechanism of steam explosion energetics,announced at 851023 Water Reactor Safety Info meeting.Requests opportunity to present results to NRC. (27 page(s), 10/29/1985)
• ML20207A534 - Forwards monthly cost-status rept for Mar 1986 for "Reactor Safety Research Program." W/o encl. (1 page(s), 4/10/1986)
• ML20207A230 - Forwards comments on APS conclusions on frequency of massive in-vessel steam explosions.Probability of failure mode may have been underestimated & for some plants represent significant cause of early containment failure. (12 page(s), 10/9/1985)
• ML20207A346 - "Experiments & Applications of Rayleigh-Taylor Instability in Reactor Safety Issues." (317 page(s), 12/31/1985)
• ML20207A279 - Extends invitation to participate in Research Review Group on Molten Core-Coolant Interactions 850828-29 meetings in Madison,WI to discuss interaction questions.Agenda encl. (70 page(s), 8/9/1985)
• ML20207A466 - "Fuel-Coolant Interaction Program," monthly rept for May 1986. (4 page(s), 6/23/1986)
• ML20207A563 - Forwards std order for DOE work for FINs A-1019,A-1030, A-1198,A-1218,A-1227,A-1246,A-1258,A-1335,A-1342,A-1389, A-1405 & A-1406. (3 page(s), 2/21/1986)
• ML20207A439 - Forwards FY86 draft program plan for fuel-coolant interactions program,per NRC program brief for FY86. (56 page(s), 1/30/1986)
• ML20207A396 - Requests discussion of possible future of vapor explosion experiments.Current experimental program to identify & measure mechanisms controlling mixing during vapor explosion in Freon-water sys progressing as planned. (1 page(s), 7/18/1986)
• ML20207A457 - Provides notes from review of "Investigation of Steam Explosion Loadings W/SIMMER-II." Objections ctr on listed considerations,including substantiation of simple scaling & role propagation plays in large mass explosions. (531 page(s), 6/26/1986)
• ML20207A182 - "Phenomenological Studies of Large-Scale Steam Explosion Efficiencies." (10 page(s), 12/3/1985)
• ML20207A538 - "Fuel-Coolant Interaction Program," monthly rept for Feb & Mar 1986. (4 page(s), 3/25/1986)
• ML20207A543 - Monthly progress rept & financial accounting for NRC Research Order 60-86-001,FIN A-2260,Task B,for Feb 1986. (3 page(s), 3/21/1986)
• ML20207A207 - Reconfirms invitation to participate in 851203 discussion at lab re vapor explosions. (2 page(s), 11/8/1985)
• ML20207A374 - Submits comments on five papers prepared by Theofanous & co-workers.Papers should not be interpreted as ultimate resolution of alpha-mode failure issue,but rather as improved organization & categorization of phenomena. (15 page(s), 8/6/1986)
• ML20207A581 - "Reactor Safety Research Program," monthly cost-status rept for Dec 1985. (3 page(s), 1/22/1986)
• ML20207A523 - Monthly progress rept & financial accounting for NRC Research Order 60-86-001,FIN A-2260,Task B,for Mar 1986. (3 page(s), 4/25/1986)
• ML20207A598 - Ack receipt of 851118 ltr re use of COREXIT facility for corium-coolant mixing experiments.Meeting suggested for 860130 to discuss comments & review technical details. (1 page(s), 1/3/1986)
• ML20207A329 - Requests review meeting to present technical results demonstrating that difficulty in measuring water phase pressure resolved.No fuel coolant interaction tests should be performed until problem resolved. (1 page(s), 7/23/1985)
• ML20207A226 - Forwards lengthy document re vapor explosions for review & comment.W/o encl. (2 page(s), 10/17/1985)
• ML20207A427 - "On Probabilistic Aspects of Steam Explosion Induced Containment Failure:Part V - Final Results." (18 page(s), 7/31/1986)
• ML20207A490 - Submits comments on "Steam Explosion Loadings Using SIMMER-II." Probability estimates subjective & calculations detailed in rept can only parameterize physics of steam explosion. (2 page(s), 6/9/1986)
• ML20207A401 - "Corium Coolant Mixing (Task A)," monthly progress rept for June 1986. (9 page(s), 7/16/1986)
• ML20207A356 - Outlines three key variables of steam explosion issues at most probable values.Optimistic views expressed in current draft NUREG-1150 cannot be sustained on basis of NRR latest results. (1 page(s), 9/9/1986)
• ML20207A266 - Lists recommendations for continuation of Sandia FCI program.In order to develop appropriate instrumentation & mechanical work measurements in more prototypical geometry, 20-50 kg scale experiments should continue for 2 yrs. (2 page(s), 8/15/1985)
• ML20207A334 - Informs that,based on Asselstine 850425 memo re steam explosions,staff believes review in NUREG-1116 provides adequate basis for position that probability of containment failure from steam explosion very low. (8 page(s), 7/19/1985)
• ML20207A377 - Project & budget proposal for NRC work: "Corium-Coolant Mixing." (5 page(s), 8/31/1986)
• ML20207A307 - "Thermal-Hydraulic Modelling & Analysis for Large-Scale Vapor Explosions." (422 page(s), 8/31/1985)
• ML20207A187 - Forwards std order for DOE work for encl listed FINs,for execution. (6 page(s), 11/22/1985)
• ML20207A272 - Submits analyses of problem set forth in 850809 memo. Experiments w/transparent simulant fluids w/range of density ratios near 10 should be used to derive correlation similar to Young. (3 page(s), 8/13/1985)
• ML20207A234 - Forwards paper entitled, "Reexam of Steam Explosion Source Term During Severe Accidents." Release from large diameter particles generated by explosion would be limited due to kinetic processes. (2 page(s), 9/26/1985)
• ML20207A529 - "Corium Coolant Mixing (Task A)," monthly progress rept for Mar 1986. (4 page(s), 4/24/1986)
• ML20207A192 - Forwards std order for DOE work for FINs A-2026-6,A-2016-6, A-2220-6,A-2232-6,A-2255-6,A-2257-6 & A-2260-6 for execution. (8 page(s), 11/22/1985)
• ML20207A319 - Project & budget proposal for NRC work: "Fuel-Coolant Interactions." (73 page(s), 7/31/1985)
• ML20207A558 - Requests work on Item 2 of FIN A-2260 proceed on schedule. Exchange of three corium-coolant mixing tests & five simulant matl jet-water mixing tests for four corium-coolant mixing tests acceptable. (1 page(s), 2/27/1986)
• ML20207A615 - Paper entitled, "Recent Intermediate-Scale Experiments on Fuel Coolant Interactions in Open Geometry (EXO-FITS)," for presentation at ANS/ENS Intl Topical Meeting on Thermal Reactor Safety on 860202-06 in San Diego,CA. (12 page(s), 2/6/1986)
• ML20207A172 - "Reactor Safety Research Program," monthly cost-status rept for Nov 1985. (2 page(s), 12/20/1985)
• ML20207A367 - Submits comment on 860722 meeting re review of alpha-mode study.Analysis presented by Theofanous based on numerous arbitrary assumptions inconsistent w/experimental observations & industrial experience. (2 page(s), 8/6/1986)
• ML20207A239 - "Reexam of Steam Explosion Source Term During Severe Accidents," presented at 851028-1101 Symposium on Source Term Evaluation for Accident Conditions in Columbus,OH. (23 page(s), 10/28/1985)
• ML20207A339 - "Heat Transfer & Fluid Flow Aspects of Small-Scale Single Droplet Fuel-Coolant Interactions." (244 page(s), 12/31/1985)
• ML20207A284 - Forwards preliminary form of proposal re corium melt stream quench behavior in water under TMI-type conditions,for comment. (1 page(s), 8/2/1985)
• ML20207A298 - "One Dimensional Transient Fluid Model for Fuel-Coolant Interaction Analysis." (182 page(s), 8/31/1985)
• ML20207A508 - "Corium Coolant Mixing (Task A)," monthly progress rept for Apr-May 1986. (4 page(s), 5/22/1986)
• ML20207A502 - "Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program,Oct 1985 - Jan 1986." (68 page(s), 1/31/1986)
• ML20207A579 - Recommends that present matrix of four reactor-matl tests be reduced to three tests for corium-coolant mixing program (FIN A-2260).Simulant matl tests will be performed under conditions analogous to reactor matl tests. (4 page(s), 2/12/1986)
• ML20207A511 - "Fuel-Coolant Interaction Program," monthly progress rept for Apr 1986. (4 page(s), 5/6/1986)
• ML20207A289 - Requests that working FCI codes used by Sandia for calculations be sent to AJ Briggs at UK-Winfrith by 850830. (1 page(s), 8/2/1985)
• ML20207A202 - "Reactor Safety Research Program," monthly cost-status rept for Oct 1985. (2 page(s), 11/15/1985)
• ML20207A568 - Monthly progress rept & financial accounting for NRC Research Order 60-86-001,FIN A-2260,Task B,for Jan 1986. (3 page(s), 2/17/1986)
• ML20207A324 - Forwards revised introduction to bimonthly progress repts, for review & approval. (2 page(s), 7/29/1985)
• ML20207A607 - "Reactor Safety Research Dept Summary of FY85 Activities & Results." (185 page(s), 1/31/1986)
• ML20207A384 - Responds to remarks made in memo to C Allen re presentation of steam explosion findings.Evidence should be provided to support innuendos that plagiarism exists in parts of rept or apology extended. (2 page(s), 7/31/1986)
• ML20207A293 - "Proposal for Investigation of Corium Pour-Stream Mixing, Quench & Debris Formation." (18 page(s), 8/1/1985)
• ML20207A390 - Comments on steam explosion work done by Theofanous re new calculations to estimate frequency of alpha-mode for containment failure.Structural calculations in Part IV of rept should be reviewed by cognizant structural analysts. (9 page(s), 7/23/1986)