NUREG-1265, Forwards Agenda for NRC Research Meeting on Core Melt Progression Scheduled for 870901-03,NUREG-1265 & NUREG/CR-4883.W/o NUREGs

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Forwards Agenda for NRC Research Meeting on Core Melt Progression Scheduled for 870901-03,NUREG-1265 & NUREG/CR-4883.W/o NUREGs
ML20237G743
Person / Time
Issue date: 07/31/1987
From: Silberberg M
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
NRC
Shared Package
ML20237G577 List:
References
RTR-NUREG-0956, RTR-NUREG-1265, RTR-NUREG-956, RTR-NUREG-CR-4883 NUDOCS 8709020391
Download: ML20237G743 (6)


Text

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. AUG 12 '97 12:20 FAUSLE_& ASSOC R P.5 ATTACm!ENT A

[p 8 \, i UNITED $TATEs NUCLEAR REGULATORY COMMISSION

$ r l WAEHING ton, D. C. 20155 -

. N.,.....f JUL 31987 TO: DISTRIBUTION A FROM: M. Silberberg, Chief Accident Evaluation Branch

SUBJECT:

NRC RESEARCH MEETING ON CORE MELT PROGRESSION, SEPTEMBER 1-3, 1987 In-vessel core melt progression plays a very important role in severe accident analysis, source term estimation, and plant risk assessment. Melt progression phenomena establish initial conditions for and strongly affect virtually all other phenomena that determine containment loadings and fission product behavior.

Our severe accident research program, including the area of core melt progression, has been under a general review for the past few years as part of the NUREG-0956 reassessment. This gereral review included specific reviews by the APS. the ACRS, IDCOR and others. Staff uncertainty papers that give excellent beckground information on the relevant technical areas were published recently in NUREG-1265. More recently, in response to a Comission suggestion, independent panels of experts (sometimes referred to as the Kouts panels) reviewed our research plans for resolving the outstanding uncertainties. The Kouts panels were asked to comment on the adequacy of our research plans for resolving these uncertainties, and they published their findings in NUREG/CR-4883.

We have reviewed the Kouts panel comments and have discussed these matters with our principal laboratory managers. In light of all of this information, we have revised the research plans and must now implement them. On the important topic of core melt progression, we are thus calling together all of our contractors, and a few others with high interest in this topic, to make sure that the detailed plans of each contractor are consistent with the everall plan and that the work is well coordinated. w In this progran area we are developing detailed mechanistic codes'to provide an analytic capability for core melt progression. We are also planning and conducting experiments to support model development and to permit code j validation. We need at this time to focus on low the experiments will meet the '

needs of our codes and medels. We also need to make sure that the right mix of in-pile experiments, out-of-pile experiments, separate-effect tests, and combined-effect tests is being utilized to best fit the specific needs that are identifieg. Your participation is important at this stage in our program as we move forward into the late phase of core melt progression and reflect on remaining needs in the early phase.

8709020391 870824 PDR RriVGP ERGIDCOR PDR

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R P.6 CW)312 '87* 12:21 FAl.GI 3 ASSOC ATTACHMENT A 2 JUL 811967 -

The enclosed agenda has been structured in accordance with the above discussion. That 15. modeling and validation needs will be discussed first, It is and then. experimental plans will be discussed in light of those needs.

recognized that, in presenting a discussion of future plans as called for many times in the agenda, it may be desirable to provide some background information on previous results. This is expected, but you should confine your total presentation to the time allotted allowing also for some limited amount of discussion. Extended discussions will be cevered by the time allotted near the end of each session. The agenda is still considered preliminary at this time If because firm commitments have not yet been received from all presenters.

significant changes are made in the agenda, we will mail a revision to you.

ThemeetingwillbeheldattheRamadaInninBethesda(8400WisconsinAvenue).

If ycu have any questions, please call Ralph Meyer at (301) 443-7615.

d M. Silberberg, C ief Accident Evaluation Branch Enclosure 1: Preliminary (Agendaunless you were on original distribution)

Enclosure 2: NUREG-1265 Enclosure 3: SUREG/CR 4853 (unless you were on original distribution) l l

R P*7 ro; 12 w wza r9us.t s asKt q.

q ATTACHMENT A -

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k IN-VESSEL CORE MELT PROGRESSION AND HYDROSEN GENERATIDN

, a RESEARCH PROGRAM REVIEW MEETING September 1-3,1987

. Preliminary Asenda Tuesday, September 1 8:30 Introduction M. Silberberg, NRC (20) '

l i 8:50 Purpose and Organization R. Meyer, NRC '

(10) of the Meeting 9:00 Research Program R. Wright, NRC l (30) Content and Status 9:30 Relevant Severe Accident P. Cybulskis,.8CL (30) Parameter Space Melt Progression Analysis Code Description Chairperson J. Mitchell, NRC l

10:00 Severe Accident Code Strategy J. Mitchell, NRC ll

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(15) <

l 10:15 General Description of J. Kelly,'NLS (15) MELPROG Melt Progression Module  ;

i 10:30 General Description of C. Allison, INEL

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(15) SCDAP Melt Progression Module va i 10:45 General Description of L. Ott, ORNL l (15) ORNL BWR Melt )rogression Model l i 21:00 General Description of V. Denny, SAIC ,

l (15) CORMLT Melt Progression Module '

l Early Phase Core Melt Progression  ;

I (up to ceramic material relocation) ,

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Chairperson R. Van Houten, NRC l

4 11: 15 Information Needs for SCDAP C. Allison, INEL

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(30) Development and Appi,1 cations ,

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AUG 12 '07 12 22 FAU5KE_& A5SGC R P.8 ATIACHMENT A 11:45 Information Needs for NELPROG J. Kelly, SNL -

(16) Development and Applications 12:00 Lunch 1:00 ' Infomation Needs for BWR L. Ott, SNL (15) Core-Melt Modeling 1:15 Infonnation Needs on Blockage A. Cronenberg, ESA (15) Formation and Hydrogen Generation l

1:30 Future Plans for PBF, LOFT, and D. Osetek, INEL (45) TMI Debris Examinations and Analysis (A2220,A6305,A6870) 2:15 Future Plans for MELPROG Validation K. Reil, SNL (45) Experiments and ACRR Posttest Examinations (A1335.A1405) 3:00 Future Plans for NRU Tests and F. Panisko, PNL (45) PosttestExaminations(B2277) 3:45 Summary of KfK Severe Fuel P. Hofmann, KfK (30) Damage Work and Future Plans 4:1C Discussion R. Van Houten, NRC (2:30) (moderator) l 5:15 Adjourn Wednesday, September 2 8:30 Discussion - continued 10:00 Suming Up of important Points R. Van Houten, NRC (30) About Early Phase Research Plans Late Phase Core Melt Progression o Chairperson R. Wright, NRC 10:30 Sumary of Late Phase Results R. Hobbins, INEL (30) Froni the TMI-2 Core Examination 11:00 Information Needs for MELPROG W. Camp, SNL (45) Development end Applications II:45 Information N e ds for BWR S. Hodge, ORNL (15) Core-Melt Modeling 1

12:00 Lunch 2 .

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Al%; 12 '87 128 22 FAUSKE_& ASSOC R P.9

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ATTACHMENT A 1:00 Information Needs Based On C. Allison, INEL -

(15) INEL Experience 1:15 Future Plans for late-Phase K. Reil, SNL (45) Out-of-PileExperiments(A1405) 2:00 ' Future Plans for ACRR Late-Phase K. Reil, SNL (60) Melt Progression Experiments (a) Expertence with the DC-1 and K. Reil, SNL DC-2 LMFBR Debris Bed Melting Experiments R. Gauntt, SNL (b) Plans for the MP Test Series 3:00 Future Plans for TMI B. Cook, INEL (15) DebrisExamination(A2220,00E) 3:15 Discussion R. Wright,)NRC (2:30) (moderator f 4:45 Adjourn l

Thursday, September 3 -

8:30 Discussion - continued 9:30 Summing Up of Important Points R. Wright, NRC (30) About Late Phase Research Plans M_elt Progression Analysis Codes -

Plans for Development and Validation 10:00 Plans for Development and Validation of W. Camp, SNL (60) MELPROGMeltProgressionModels(A1342) 11:00 Flans for Development and Validation of C. Allison, INEL (30) SCDAPMeltProgressionModels(A6360) 11:30 Plans for Development and Validation of S. Hodge, ORNL is .

(30) ORNLBWRMeltProgressionModels(50452) 12:00 Lunch 1:00 UK Ex grience with Mechanistic 5. Kinnersly, WIN (30) Melt )rogression Code Validation 1:30 Posttest Calculations with the K, Matsumoto, JAERI (30) MELPROG Code 2:00 Status of CORMLT Code V. Denny, SAIC (30) Development and Validation 3

. AUG 12 '87 12823 FAUSKE & ASSCC R P.10

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ATTACHMENT A l

2:30 Discussion J. Mitchell, NRC '

(1:16) (Moderator) 1 3:45 Suming Up of Important Points About J. Mitchell, NRC j (30) Modeling and Validation for Core Melt Progression Analysis 4:15 Adjourn 1

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