ML19345G402
| ML19345G402 | |
| Person / Time | |
|---|---|
| Issue date: | 01/14/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1800, NUDOCS 8104070176 | |
| Download: ML19345G402 (5) | |
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Date Issued: Jan 14 1981 ACRS SUBCOMITIEE ON ADVANCED REACIORS WASHIBUION, D.C.
DECEMBER 2, 1980 The purpose of the meeting was to discuss the W 1982 budget in preparation for the annual report et the ACRS to Congress on the NRC Research Budget. The prin-cipal attendees at the meeting were as follows:
M. Carbon, Chairman J. C. Mark, Subcorrmittee nember R. Savio, ACRS Staff C. Kelber, NRC Staff R. Curtis, NRC Staff T. Walker, NRC Staff M. Silberberg, NRC Staff R. Foulds, NRC Staff The meeting was closed and was not attended by any cembers of the public.
Dr. Kelber sumarized the status of the W 1982 budget in the advanced converters and fast breeder reactor areas. DOE mark on the W 1982 budget has not been re-ceived. The Cam:ission has, requested for W 1982 in accordance with the GIB l
guidance $2.0 million for advanced converter reactors and no funding for fast breeder reactors. The funding request for fast breeder reactors is conditioned such that a funding level of $8.0 million (in addition to the rest of the RES W 1982 budget) is res asted if DOE maintains a significant development effort on IFEBR development. The Congress may restore funding for fast breeder reactors.
The ACRS has reconmended that the fundini; level for fast breeder reactors be
$17.5 million. The budget request for advanced converter reactors was discussed.
A funding level of $2.0 million was requested in accordance with the O!B guidance.
It is expected, however, that the portion of this work which is being conducted in support of Ft. St. Vrain will have been completed by W 1982 and that there will be no significant and perhaps no DOE development effort in this area.
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Advanced Reactors Deceaber 2, 1980
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does not appear that there will be such an initiative in this area in the near future. Opinions were expressed that on this basis there is a good rationale for not funding this area in FY 1982.
A decision on a DEBR daaonstration plant is expected in FY 1982. The two rest likely possibilities are a continuation of CRBR or the increased funding of and timely construction of CDS. The funds already spent on the manufacture of CRBR hardware and CRBR design would be expected to influence this process. Opinions were ex-pressed that the level of IER and RES resources which would be allocated to the DFBR effort under the current NRC plans would not support an early licensing effort. The work conducted on fast breeder reactors at the $8.0 million level would be expected to be supplaaented by Class 9 accident work conducted in the ILR area. At the $8.0 million funding level the work in the IlfBR area would emphasize the HCDA/SIMER work, risk ~ analysis, the BRENDA/SSC code work and the containment analysis / sodium fire work.
STAIUS OF ANALYSIS WORK - R. CURTIS,IEC The accident delineation work is essentially complete. The study concluded that j
the greatest contributor to risk was from the accident with scram. Risk sssoci-f ated with loss of flow accident was significantly greater than from the transient over power accidents. The study concluded that local fault propagation was un-likely but that this phenomena could not be disregarded. Base mat failure was i
found to be the most likely node of contairraent failure.
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4 Advanced Reactors Dece:ter 2,1980 Ihe SSC-L Cods is operational and has been used to prepredict the FFIF natural convection tests. The FFIF 5% power natural convection tests have been run but the data frcxn these tests has not been ccr:pletely processed. At this stage the SSC predictions appear to be adequate lut final judgent will have to await the further processing of the test data. The SSC-P is operational and has been used to model the PHENIX reactor. The double-ended pipe rupture and the coast-down to natural circulation transients have been codeled. Results appear to be reasonable but the available test data is not adequate to fully judge the results.
The SDER code-has been used to study a 1000 m'e heterogeneous core similar to that which is expected to be used in the CDS. The code has also been used in Ua core celt studies (Zion / Indian Point) and fuel pin test assesly analysis.
A significant R&D need will be for a better or generalized understanding of the modeling of freezing / bugging phencxaena.
STAIUS OF IE AEROSOL FNASE #3 TRAMPORT/ACCIDET ELNCS/SYSIDS ILTEI;RITY WORK - M. SIIEERBERG, 'aC The aerosol release and transport work that is currently undersuy is directed towards the understanding of the liCDA aerosol source term. This includes fuel vaporization tests in the FAST facility (CRNT), bubble dynamics modeling (OiC1, WA), and studies directed at the understanding of the formation of sodiu:a/plu-toniucr-ccx pounds 9 A conditions (Mound Laboratory). Future w rk, if funded, will be directed towards underst:sading of the core celt uurce ter=.
Separate effect tests, related to the understanding of filtered vented contaia-cent syste=s, could also be condu:ted in the NSPP facility (CEC 1). The HAAm!-3 code has been used to predict aerosol agglameration tests conducted in the NSPP facility.
4 Mvanced Reactors December 2, 1980
%e accidents energetics work at Sandia is continuing as per the program plan.
A cooperative agreemnt with FRG-Kfk is expected to be finalized in the near future. Fuel dynamics and work potential experirents are being conducted in the ACRR facility. Transition phase experirents are being conducted at BNL and at Sandia. Le BNL program consists of out-of pile experiments eyWning boiling pools and fuel-freezing phen - na. H e Sandia experiments are in pile and out-of pile tests treating fuel stredng and freezing, he fuel dynamics work is being conducted in the ACRR at Sandia and treats proc:pt burst and loss of flow, irradiated dispersion experiments, and equation-of-state experi:ents. B e plan exists a build a flowing sodium loop for conducting in pile fuel dispersal experirents if sufficient funding is available. The system integrity work is directed towards elevated temperature assessments and assess:ents of potential threats to containcent integrity. The latter include studies of core debris be-havior, molten coal technology, core retention assesscent technology and sodium /
concrete interactions. An agreement has been signed for joining IEC, EEC-ISPRA, and PNC cooperation in a debris bed coolability program for the ACRR. The work is expected to be funded at a $5.0 million level over a four year period.
The codifications of the large melt facilities have been completed and a new melt crucible has been ordered.
ADVAFCED (DtWERIERS PROGRAM - R. FOUIDS, NRC Funding in this program is directed entirely at gas-reactors research and the bulk of this work (about 75%) is in support of Ft. St. Vrain liccnsing. It is expected that the work in support of Ft. St. Vrain will be cocpleted in FY 1981.
3 The FY 1981 program emphasizes high temperature properties and fatigue testirg
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Mvanced Reactors Deca:ber 2,1980 of materials, graphite corrosion, and fission product transport experirents and is being carried out at IASL, OPE, and PNL.
- t.uM-nw s+:k s*,w s*kee.<keesseeaecu-w skx-Mditional. details are available in the meeting transcript on file in the lac Public Doctrent Room,1717 H St., N.W., Washington, D.C. or from Alderson Reporting, Inc., 400 Virginia Ave, S.W., Washington, D.C.
A ccraplete set of all sitdes used are on file in the ACRS Office with the record copy of the minutes.
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