ML19341B341
| ML19341B341 | |
| Person / Time | |
|---|---|
| Issue date: | 09/11/1980 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1757, NUDOCS 8101300760 | |
| Download: ML19341B341 (19) | |
Text
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DATE ISSUED:
Ag VANCE0 REACTOR' SUBCOMMITTEE SEP 11 G80
.$.ylNUTES OF THE AD
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JU4E 13, 1980 WASHINGTON, DC
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13, 1980 to discuss the ACRS Advanced R actors Subcomittee met on JuneThe Department of E NRC-sponsored'research on advanced reactors.
d gave presentations on their LMFBR developments / safety progra Notice of this meeting for the ACRS review of the NRC sponsored research.
- 15. 1980 and May 29, 1980. Copies was published in the Federal Register of May The schedule for this meeting of these notices are included as Attachment A.
is included as Attachment B and a list of attendees Portions of the material provided to the Subcommittee at this weeting a The comlete set of material provided to the Subcom-included as Attachment D.
No oral statements 'were given by metters of the mittee is in the ACRS files.
tatements public nor were there any requests for time to give submitted.
The Designated Federal E g loyee Chair: nan, Dr. W. Kerr, and Dr. J. C. Mark.
was Dr. R. Savio, ACRS Staff.
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2 INTR 000CTIOff O'JERVIEW OF PROPOSED BUDGET T. MURLEY, S. C. KELBER, NRC d
Dr. Hurley and Dr. Kelber sumarized the projected funding for the Adv The OMB budget for FY 81 Reactors research (See Table I of Attachment D).
d allots $5.0M for Fast Breeder Reactors (FBR) and Converters.
The Congressional Budget for this area research on Advanced Reactors in FY Bl.The Senate Com has not yet been finalized.
Works has authorized $22.5 M to the NRC for Advanced Discussions are still ongoing in has not increased the overall RES budget.Dr. Murley and Dr
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The budget for Advanced Converters is expected to be small as it Congress.
If funded, the Advanced Converter program will be for FBR.
has been in the past years.
If a decision is made to directed toward work in support of Fort St. Vrain.
ld be re-terminate the Advanced Reactors research for FY 81, the progr directed as soon as possible in FY 80.
l be budget, but not at the termination l'evel was authorized, the emp l
placed on maintaining critical segments of the program and critical pe It is likely that, with the reorientation of the LWR program toward the technology, a good part of the core melt technology being funded under Advanced Reactors research program would now be funded'under the l
views the critical areas within these programs as being the LMFBR f interaction RES melt activities, including the debris bed work, the fuel concrete k
It is thought work,theaerosolsourcetermexpriments,andtheSIMERwor.
ition that the SimER code could evolve into a useful tool for modeling the tra The expertise within NRC for managing core melt orientated l
It is expected phase in LWRs.
l research programs is in the Advanced Reactors research program.
(about505) f that given the proper amount of financial support a substantial part of the Advanced Reactor safety research technology will be redire f
When this the degraded core cooling problems in connection with the LWRs.
't Y 82 and ll program redirection takes place, RES expects to propose funding in A breakdown of'the funding beyondasdirberibedinTable2ofAttachmentD.
for residual LMFBR activities is sumarized on page 1 of Attachment D.
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4 FBR ANAYSIS PROGRAM - R. CURTIS, NRC/RES
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Dr. Curtis'sumarized the analysis work being carried out under these COW!IX/
The major segments of this work are the SSC codes, the SI!HER code, There are currently four BODYFIT codes,' and the accident delineation work.
i nts (up versions of the SSC codes, the SSC-L code simulates short-term trans e l since September to one-half hour) in loop-type LW BRs and has been operationaFBRs of 1977, the SSC-P code simulates the short-term transients in poo l
short-and has been operational since November 1979. The SSC-W code simu a The SSC-W term transient in LWRs and has been operational since March 1980.
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d code has the capability for treating only the liquid phase.. The SSC-5 co done-halfhour)is which simulates intermediate to long-term transients (beyo not yet operational.
l The the FFTF loss of flow test and has been found to yield cercarable resu ts.
SSC code has been used to prepredict these FFTF tests and will b The COMMX-1 code (3-dimensional, one-against the test results when available.The COMMIX-2 code (3-dime phase) is-operational.
Accident BODYFIT codes (geometry transform codes) are not yet operational.
Phase 1 of this work delineation work is being carried out at Sandia Labs.
(involving the construction fault and event trees for the CRBR system The work is currently in the Phase 2 fault tree quantification base.
Work has been recently initiated on a 1000 MWe system. Wit,h charac plete.
are felt will resemble the final DOE Conceptual Design System {CDS) reac The SIMMER-2 code is released and is in use in tt e'
.S., the FRG l
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. Studies are underway at Sandia which are directe concept.
UK, Japan, and within ISPRA.
t towards studying the CRBR recritic~ality and HCDA phenomena in a 1000 The design has the heterogeneous core and is typical comercial LMFBR design.
a loop-type plant similar to the 00E CD'S concept.
FBR-AEROSOL RELEASE AND TRANSPORT PROGRAMS - M. SILBERBER Mr. Silberberg discussed the work being sponsored on aerosol rele The objective of the work is to develop data and analysis metho assessing thi radiological consequences of severe accidents and the eff Work directed towards of mitigation features on radiological consequences.
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assessing the HCDA source term is being carried out in the FAST facil Work ORNL and in ~modeling efforts at ORNL and the University of Virginia.
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- the development of at the Battelle-Columbus Laboratories is directed towards i tion of aerosol aerosol behavior model (HAARM-3 code) and the cha The. work properties.The FAST facility is a one-tenth scale vessel simulation.
at ORNL, i tion of the 002 (by that has be'en carried out to date has involved vapor zaThis aspect of the w capacitor discharge techniques) underwater.
l aporization of pleted and, if funded, the next series of tests will invo l ted. The fuel in sodium.
towards the basic validation of the HAARM-3 code, has been com work to date has stressed HCDA conditions.
interest to core the work will be redirected toward the conditions of m Aerosol results to melt conditions.
Laboratory on the chemical characterization of the HCDA.
factor of 10 lower date have indicated that plutonites fonnation is at least a for HCDA conditions and fraction assumed for the FBR l
would be implied by one percent plutonium re ease safety reviews conducted to date.
FBR-SYSTEM INTEGRITY - M. SILBERBERG, NRC/RES_
The programs are Mr. Silberberg summarized the system integrity programs.
debris behavior, directed towards elevated temperature design assessmept, core
'i s The elevated molten core technology, and sodium concrete interact on.
ry low funding temperature design assessment work is being carried out at a ve Il i ry level and is directed towards est'ablishing mate t
The core debris behavior molten core technology, and so system integrity.
to contain-interactions work is directed toward assessing the possible thre at DOE.
9 ment integrity from core melts and sodium spills.
hich are performed in work consists of debris bed coolability ' experiments, w The large scale i
ts.
the ACRR, and out-of-pile thermite fragmentation exper menbility for melt melt facility'has recently been completed and has a capa ill be tested in up to 200 )p. Concrete and candidate barrier mate This work this facility.
.models for concrete behavior.
and the development of reaction is being conducted at the Sandia Laboratories.
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. 00E PRESENTATIONS _
XNTRODUCTION F. GAVIGAN, DOE The effort was funded at Mr. Gavigan sumarized the DOE safety program budget.
The President's
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$51.8 M in FY. 78, at $37.8 M in FY 79, and at $36.5 M in FY 80.The auth budget for FY B1 calls for a funding level of 522.3 M.It is noted that appropriation bills are respectively at $39.D M and $37.0 M.
t of the level of funding in the President's budget implies early close-ou The prograrcs are managed from the headquarters organization The Technical Management Center the program.
through the Technical Management Center.
Financial h
interacts directly with the National Laboratories and contractors.
h direction comes from headquarters directly into the. field offices with t I
The DOE benefit of the recommendations of the Technical Management Center.
)
These safety programs are organized along the four Lines of Assurance (LOA i
i con-are LOA-1 (prevent accidents), LOA-2 (limit core damage). LOA-3 (ma
)
A sumary tainment integrity), and LOA-4 (attenuate radiological consequences.
2 of Attachment D.
The bulk of the of the current projects is given on page LOA-2 and LOA-3 proposed FY 81 funding (at an assumed $37.0 M
($4.5 M).
($4.5 M), and LOA-2 ($11.5 M), LOA-3 ($14.0 M), LOA-4 ($2.0 M), RI.D integration areas.
facility development ($0.5 M).
DOE TEST F ACILITIES - R. J. D'0WLING, DOE ilities. These were Mr. Dowling gave a brief discussion of the major DOE test facThe T TREAT, the TREAT Upgrade, ETEC, and ETR/SLSF.
ditions cooled thermal reactor that was designed to test reactor fuel under con i l in simulating various nuclear transients., The facility first went crit ca The DOE is currently funding an upgrade of the TREAT February of 1959.
f The modified f acili1!y would'have the capability of testing up to 37 The LMFBR fuel assemblies under prototypical conditions.
i Energy Technolatgy Engineering Center (ETEC) is located in Ca ETEC was established in 1966 as a mately 14 miles northwest of Los Angeles.
d Government dened/ contractor-operated laboratory to provide facili ETEC has conducted engineering services for the developers of the LMFBR.
l sodium proof testing on heat exchanaers, steam generators, pumos The major facilities and control instrumentation for major LMFBR components.
6
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at ETEC are:
The $ mall Components Test Loop
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3)
The Large Leak Test Rig 4)
The Thermal Transient Facility 5)
The Static Sodium Test Facility.
6) 3 & 4 of Attach-The characteristics of these facilities are sumarize l t d in The modifications of the ETR facility for the SLSF loop were cong e e ment D.
i s of transient November of 1975.and the facility has since been used LMFBR fuei pin tests.
The House appropriations bill at, respectively, $1.2 M, $21.1 M, and $7.6 M.
t $18.0 M.
for FY 81 funds the TREAT operations at $1.8 M, the ETEC ope and requires close out of the ETR operations.
TREAT operations Committee appropriations bill for FY B1 calls 'or a funding of at $2.0 M, ETEC at $21.0 M, and ETR at $6.5 M.
00E PLANT PROJECTS - F. GAVIGAN, J. LONGENECKER, DOE _ -
l Fuel load was; initiated in Mr. Gavigan summarized the status of the FFTF.
i on February 9, 1980.
October of 1979 and the reactor achieved initial criticalit Full power o 15, 1980.
Zero power physics tests were co[npleted on March l tion design is expected in late 1981, with performance of the natura power tests in November 1981.
In total estimated cost for project and the Conceptual Design Study project.The project td the CRBR is $2.9 billion.If funding for the project is authorized a 1988. Under this that the initial criticality could occur in September of 1989 to April 1994.
FY 70.
schedule the plant operating period would be from April d
tages and The project is intended as a demonstration of the environment The major electrical energy resource.
a economic potential of LMFBRs as The equipment development and design at this point is about 78% complete.An completed end on order totals.$500 M.
The Final Environmental for equipment if the croiect is to be comoleted.
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. The Statement and site suitability repcrts were issued by NRC in early 1977 The environmental hearings on the project were susp'nded in March of 1 NRCiscubentlynotpursuingthesafetyreview.
The Conceptual Design evaluated their activities in light of post THI reviews.
Study was irrit1ated as a result of the April 1977 administration LMF The policy was directed towards the deferral of the commercializa-Research and developmnet statement.
f tion of the LMFBR and a cancellation of CRSR and PLBR.
l effort was to be conducted at such a level as to keep the LMFBR optio The NASAP and INFCE studies were initiated and now for the most A report on the The Conceptual Design Study was initiated in October 1978.
h The plant completed Conceptual Design is to be made to Congress in April 1981
[
is to be a 1000 !We, four-loop-configuration plant.The schedule for design an a heterogeneous core with mixed oxide fuel.
construction of this facility was approved is on page 5 of Attachment D.
DOE LMFBR SAFETY PROGRAM F. GAVIGAN, DOE The program goal is to Mr. Gavigan sumarized the DOE LWBR safety program.
design and provide a technology base to support safety considerations in the licensing and economic optimization of LMFBRs.
The projects being the LOA-1, LOA-2, LOA-3, and LOA-4 lines of assurance.
carried out under the four lines of assurance are as follows:
- 1) LOA Prevent ace'idents Reactor system reliability studies a)
Reactor shutdown sys' tem reliability studies.and tests b)
Shutdown heat removal system reliability studies and tests c)
- 2) LOA Limit core damage Reactors shutdown system-f ault combination a)
Shutdown heat removal system fault accomodation b) c) Local f ault accomodation LOA Maintain containment integrity 3) a) E'nergetics accommodations b), Debris accomodation
- 4) LOA Attenuate radiological consequences a) Engineer attenuation b) Inherent attenuation The individual program elements are su'mmarized in Attac.hment D i
'MOG pm,
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8-NRC PRESENTATION (CONTINUED 1 ADVANCED CONVERTERS PROGRAM - R. FOULDS, NRC/RES k was Mr. Foulds indicated that the major part of the Advanced Converter
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directed towards the Fort St. Vrain reactor.
The programs currently bility and could be expanded if funding were available.
nd in place address, for the most part, the structural integrity of the co A summary of fuel behavior and place considerable emphasis on graphic behavior.
.this work is given on page 6 of Attachment D.
Mr. Peter Williams, NRR, commented briefly on the RES Advanced C h
He noted that NRR agreed that the Fort St. Vrain reactor k
should be given the first priority and indicated that NRR would endor research program.
i.
in the following areas, funding permitted:
The degradation of the strucural graphite in the temperature / stre f
environment and the development of design criteria for this type o 1) application Seismic response of core graphite 2)
- 3) Fuel transient response Inservice inspection of core graphite 4)
Natural convections studies 5)
Mechanisms of fissfon gas release and transport' 6) y Prima.y system barrier performance 7)
Advancedinserhice'inspectiontechniques 8)
Effects of helium enYiroriment on the properties of the primary 9) system steel A WASH-1400 type analysis of the HTGR.
10)
The meeting was' adjourned at 5:30 after this presentation.
b h NRC Additional detail is available in the meeting transcript of file in t A complete set Public Document Room at 1717 H Street, N.W., Washington, D.C.
f of slides presented is on file'at the ACRS office with the record c the minutes.
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i 29, 1980 / Notic:s
_ g Federal Register / Vol. 45. No.105 / nursday. May tsuneditly,and the WeM,ts given esassions would not b possible if held to an opportunity Mow asase wny &
public wums in ed6non.n sney be bcense should not be revoked. In Advisory Committee on Meector escenary for the hhcomminu a hold one accordance with the Order, all Ihensed Safeguares Subcommittee on Advanced Neactors, Meeting er esore closed sessione for the purpose of material has hen properly transferred.
a he ACRS Subcommittce on g
sa,n ego ne Order provided the licensee Advanced Reactors will bot a meeting eceordance with Subsecton to(d) of theapportunity to We a written answerth Federal Advisory Comsuttee Act (PA L 82-on Fnday. June 13.1980 tn room 1046.
1m H Street NW, Washington.D.C.
anal. that. should such eessions be requind. It the date of the Order. and stated that as accesury to close portma of this meetr4 upon tMim's failure to file answer 20555. Notice of this meetag was to prevent trustrenan of the above easted g.
I aspect of h ACRS'steeutory respoemibahneewithin the specifie time.
pubbshed May 15.1980.in accordance with the procedures and to protect propnetary information. See 5 Office ofInspecnion and Enforcement.
outimed m the Federal Resister on U.S.C.mblettetsi and 55:h(cg October 1.1979 (44 FR 56406) oral or neokmg the Ee rs of t$e p bSc.te
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i, be permitted only during those portions has been cancelled or rescheduled.theWy b
1 of the meetmg when a tranacnpt to being Chairman's ruling on requests for the g
opportunity to present oral statements d te 5censee' kept. and questions may be asked only by members of the Subcommittee.Its and the tirne allotted therefor can be ans er the Order.It is hereb fa0
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Nake or 1s stem r[ts ouldn$
y Mosase 21-P E2/634-3287) between 4;15 a.m. and 5 Deted et BetheeJa Maryland es teth day in e a.ce e p a tacab o
tppropnate arrangements can be made P "-
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to allow the necessary time durms the Dated; Msy za.1sso.
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1 De agenda for subject meeting shall )mba C. hpe.
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Adeisory comminee Management 0Wiar.
be as follows:
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ggyproduct tastedal Ucense ten. 21-tS456-R;"-4"r.= for uoenses To Esport business.
De Subcommittee may meet in Executive Session, with any of its et,gA-to 121 seussear FacdBtles er Materials l
Pursuant tole OR 1103c(b)"Public
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Notice of Recerpt of as AppHcat>on".
explore and aschange their prelimmary l(
Order Revoeg Usense ase take notics est the Nacieer opinions regarding matten which should story Commission has received the be considered acnns the meeting.
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At the conclus:en of the Ezeeutive American X. Ray and Inspection acenses for the pened May1 through Session, the Subcornmittee will bear incorporated. Ze030 Haggerty Roed.
y,y go,1geo. A copy of each application presentations by sr.d hold discussionswith representatives of the NRC Stdf.
FarmmgtonIhus. Michigan eso?,(the is on fDe in the Nuclear Regulatory I
their consultants and other sterested
.g;c,3,,,-)is the holder of Hyproduct Comuniesion's Public Document Room Persons regardmg NRC funding andMaterial Ucense No. 21-15455-01 (the, ~1ocated at 1m H Street NW.
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program direction or program
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Regulatory Costmission (&e Dated &as (sy.Mey 18.1555, et Bethseda.
termination. as appropnate.
" Commission"), %s present exptration De ACRS is reqmred by Section 3 of the date ( the license la December FL 1s83.
par b heleer"Q Commission.
s ters NRC Authonsstion Act to review the i
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PROPOSED SCHEDULE ADVANCED REACTORS SUBCOMMITTEE WASHINGTON, D.C.
JUNE 13, 1980 8:30 - 8:45 EXECUTIVE SESSION l
)
!F.C PROGRAM Budget overview - FY 80, FY 81, and proposed FY 82
[
8:45 - 9:45 (1) and beyond (CLOSED SESSION) - C. Kelber Discussions to include an update on budget status, and FY 81 plans, action on ACRS recommendations, summary of ARSR program goal and achievements FBR - Programs (Discussions to include disruption of program elements, individual program goals, achievements, (2) and expected direction a) Analysis - R. Curtis 9:45 - 10:25 Break 10:25 - 10:40 b) Aerosol Release and Transport - M. Silberberg 10:40 - 11:00 c) System Integrity - M. Silberberg 11:00 - 11:30 Lunch 11:30 - 12:30 DOE PROGRMS F. Gavigan 12:30 (1) Introduction R. Dowling 12:40 (2) Facilities o TREAT o TREAT Upgrade o ETEC o ETR/SLSF F. Gavigan
~
1:00 (3) FFTF J. Longenecker 1:15 (4) CRBRP J. Longenecker I
(5) CDS l
1:30 1
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l F. Cavigan/TMC 1:45 4:00 (6) LMFBR Safety Program o LOA 1 1:45 o LOA 2 2:15 o LOA 3 2:45 o LOA 4 3:15 LOA Integration o
3:45 G.Welshans 4:00 (7) Gas Cooled Fast Reactor Safety Program NRC PROGRAM (C0fCINUED)
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(2) FBR Programs (continued) d) Materials Interaction 4:30 - 5:00 R. Foulds 5:00 - 5:15 3.0 Advanced Converters 5:15 - 5:30 4.0 Executive Session e
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ATTACHMENT D
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TABLE 1 ADVANCED REACTOR SAFETY RESEARCH BUDGET FY 80 FY 81 FY 82 FY 83 FY 84 LMFBR 13.7 5*/19.7 8.0 8.0 8.0 1.7 0*/2.0 2.0 2.0 2.0 HTGR
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- Phase out budget recommended by OMB
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t TABLE 2 l
FY 82 LMFBR BUDGET - $8.0 LEVEL 5
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$1.4 M l
Natural Convection 1.4 M i
Accident Delineation j
13M Fuel Testing /Whole Core Accident Analysis l f 2.9 M,-
l SUMER Verification
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TABLES 1 & 2 9
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RESIDUAL LMFBR ACTIVITIES
$1A00,000 l
STUDIES WiTH SSC, COMMIX, BREND^,.PF IFSIS j
NATURAL CONVECTION r
AT FFTF, PFR, PHENIX;
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ANALYSIS OF TEST FACILITY SCALING
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$1A00,000 n
ACCIDENT DEllHEATION 5
FAULT TREF CONSTRUCTION AND ANALYSIS, SYSTEM ANALYSIS AND COMPARISDNS SYSTEfl INTEGRITY-FAILUFI MODES O 00,003 FUEL TESTING NEEDS AND WHOLE CORE A
'SAS, EPIC, AND SIMMER STUDIES OF SENSIT OF ACCIDENT; EFFECT ON CONTAINPENT OF FUEL MODELS I
$2,900,000 Sil?1ER VERIFICATION AND RELATED TE BUBBLE EliTRAINENT, FUEL'EDS, FCI STUDIES
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7 CORE CONSIDERATIONS (UNES OF ASSURANCE)
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LOA-4 I
LOA-3 ATTENUATE LOA 2 i'A!NTAIN RAD 10LocICAL LOA 1 LivlTCORE CCNTAINVENT CONSEQUENCES PREVENT DAMAGE IM7EGRITY (4I. -;
ACCIDENTS (3) z j
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ENG1MEERED
-ENERGETICS ATTENUATION
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- REACTOR ACCOWJ0DATION
- REACTOR SHUTOCWN (3.1).
3YSTEM 3YSTEM f AULT REUASILITY ACCOU900kT10N (1.1)
(2.1)
INHERENT 6 DEBRIS ATTENUATION
-SHUT 00EM HEAT ' ACCOMMODATION (4.2)
- REACTOR REu0 VAL (3.2)
SHUTOOWN SYSTEM F AULT SYSTEM ACCCMM00AT10N REUABluTY (2.2)
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ETEC Majnr Facilities h
both up ramp a' rid Sodium Pump Test Facility (SPTF)
Circulating sodium loop design temp.1080'F,18 inch diameter pipe, with o
down ramp transient capability.
onents.
Designe'd to test large sodium pumps, large valves..flowmeters, pipe and othe 1
o l
Has tlisted the FFTF prototype pump at 14,500 gpm.
ility from 24,000 gpa Modifications both underway and planned include increasing flow capab o
7 to 45,000 gpm to 100,000 gpm in two steps.
l o
tional inducer Future test plans include retest,of FFTF prototype pump with Atomics Interna 45,000 gpm, and two and impeller assembly at 14,500 gpm, the CRBR double suction pump at o
100.000 gpm.
large plant pumps, one pr4aary and one secondary, at i
Sodium Component Test Installation (SCTI)_
l 4
l Orginally a 35 MWt Thermal Facility, now upgraded to 70 MWt capacity, d verify Designed *t'o'eva'luate thermal and hydraulic characteristics of steam generato l
o i
their controllability and structural i
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flow upsets transients.
l expansion Also used' to test heat exchangers'and various in-line components such as va ves l
3 f, low instrumentation.
TF a'ir cooled joints, and pressure, level ant' o
At 35 MWt capacity has tested the AI " hockey stick" steam generator and an FF l
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f
'o dump heat exchanger. -
rator, a Future test plans include testing a prototype and plant type CRBR steam gene b
b team generator.
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B&W helical cof1 steam generator and a. Westinghouse double wall tu e s o
i e
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- l 0 F design
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,,s' (SCTL1 ith a 3,500 gpm pump,1,200d immersion testing.
Components Test.toop Circulating loop with 8 inch and 10 inch main piping wFacility can pr
...$nall I'o temperature.
Used to test valves, small pumps, fuel handling machines, co test loops to increase f a Future plans call for separating the existing loop into twoi.e., ability to test a pu o
flexibility',and test capacity, loop which has its own facility pump.
o are being tested in the second led down LMFBR secondary-sodium i
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Large Leak Test Rio (LLTR)_
A sodium-water reaction (SWR) test facility comprised of a scah l
tm o
r Test results are used to validate and/or modify analyttcal tec n qteam generator an l
the consequences of major sod,tum-water reactions on a s I
o d SWR tests are now underway on system components.
Six SWR tests on an Al modular steam.have been completed an i
p a large diameter prototypic LMFBR steam generator.
i o
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dium) transtant temperature Thermal Transient Facility (TTF)_
i A large hydraulic loading structure permits s Used to simulate the effect of process fluid (especially so 0 F with about conditions upon plant components.
o gesigntemperature1,200F per second d mechanical and thermal stress testing, or inadvertent failure of a component 'during a test.F per second m l
are conventional bfmetal construct 0
11 t
presently life testing CRBR steam generator nozzles to comp i
il o
e) used for instrumentation-i Static sodium Test Facilities (SSTF) t Eight static test rigs (1,200' F maximum operating tempera ur d test small flowmeters, to obtain data on apor, and provide environmental testing and evaluation, including calibration an i o
mechanical devices operating in sodium and/or sod um vconditio Se'If Actuating Shutdown System haf t seal assembly),
One facility is presently used to test the safety programt d by rapid up ramp temperat with an articulated control rod assembly actua e e
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LMFBR PROGRAM LEVEL O SCHEDULE 1
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