Progress in Safety Systems for Advanced Water-Cooled Reactors (IAEA TECDOC-872)

369 Pages·1996·23.139 MB·English

IAEA-TECDOC-872
Progress in design, research
and development and testing of
safety syster moafds vanced
water cooled reactors
Proceedings of a Technical Committee meeting
hen lPdi iacenza, Italy, 1y 6a1-M9199 5
INTERNATIONAL ATOMIC ENERGY AGENCY
The originating Sectif ootnh is publie cIhAattE ionAin was:
Nuclear Power Technology Development Section
International Atomic Energy Agency
Wagramerstrasse 5
P.O. Box 100
A-1400 Vienna, Austria
PROGREN DSIES SIGN, RESED DANERVCAEH LOPMENT
AND TESTING FOS AFETY SYSTEMSR OAF DVANCED
WATER COOLED REACTORS
IAEA, VIENNA, 1996
IAEA-TECDOC-872
ISSN 1011-4289
© IAEA, 1996
Printed by the IAEA in Austria
April 1996
FOREWORD
e hTTechnical Committee Meetingn o Progressn i Design, Research& Development
and Testing of Safety Systems for Advanced Water Cooled Reactors was held at the ENEL
Training Centre, Piacenza, Italy from 16 to 19 May 1995. The meeting was convened by
e Inhtetrnational Atomic Energy Agency (IAEAe )I Ae whff raEhiaocttmAht tiiv ef'n siotie s
International Working Grn oAuodp vanced Technolor gWoiefas ter Coolesda Rwe adcntoars
a jointe hIaActtE ifvAoity's Nuclear Power Technology Development eShetc tfioon
Divisf iNooun ce lEehantrg iPdnoenwearein rg Safetye D hSitve icf sftiNioooounn clear
Safety. IAEA activities in advanced technology for water cooled reactors serve to provide
an international source of objective information on advanced water cooled reactors and to
provin diane ternational forr duoimfs cusd srineoavn ief towe chnical informatn irooens earch
and development activities.
Heat removal systems for evolutionary designs (advanced reactor designs which
achieve improvements over existing designs through small to moderate modifications) require
at most only engineed rcnionang firmatory testing. Heat removal syster dmoefsv elopmental
designs (advanced reactor designs which range from moderate modificatiof no existing
designo ste ntirew lednye sign conceptsn i)g eneral require more extensive testindnga
demonstration to verify component and system performance. Key issues are scaling effects
for simulated plant configurations, componed nsnyat stem reliabilities, agind ignna, teractions
among different systems. Furthermore, a key activity is validation of the computer codes
used for design and safety analyses of advanced water cooled reactors by comparison with
experimental test data.
The meeting cove efhoreltldo wing topics:
Developmenn tdis esig fosn afety-related heat removal componed nnstays stermofs
advanced water cooled reactors.
Staf ttouess t programn mhoeeas t removal comp wodd neseenysnnisagtt se nfmso.s
Range of validity and extrapolation of test results for the qualification of
design/licensing computer modeld snac oder sofa dvanced water cooled reactors.
Future needs and trends in testing of safety systems for advanced water cooled
reactors.
f heoat rTeems otsval safety systems have be yenv arcbioonuds ucgtre odups
supportinge ht design, testingd na certificationf o advanced water cooled reactorsehT.
Technical Committee concluded that the reported test results generally confirm the predicted
performance features of the advanced designs.
EDITORIAL NOTE
n pIreparing this publicar tpoiorfne ss, stae fIfhA EtoA f he pahavetg e mpse aufhrdote m
original manuscripts as submitted by the authors. The views expressed do not necessarily reflect those
of the governments of the nominating Member States or of the nominating organizations.
Throughout the text names of Member States are retained as they were when the text was
compiled.
The use of particular designations of countries or territories does not imply any judgement by
the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and
institut eidoh renootlsf imitation of their boundaries.
The mention of names of specific companies or products (whether or not indicated as registered)
does not imply any intention to infringe proprietary rights, nor should it be construed as an
endorsr ermeoe e cIpeAonha hEmtrAtmtt .oe fnndaotio n
The authors are responsible for having obtained the necessary permission for the IAEA to
reproduce, translate or use material from sources already protected by copyrights.
PLEASE BE AWARE THAT
E MHTIAS FSLOILN G PAGN ETISH IS DOCUMENT
WERE ORIGINALLY BLANK
CONTENTS
SUMMARY OF THE TECHNICAL COMMITTEE MEETING
OPENING ADDRESS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.1. ..
. LNoviello
STATUS AND PLANS OF DEVELOPMENT AND TESTING
PROGRAMMES (Session I)
The programm feoa dvanced light water reactorn siS pain . . . . . . . . . . . . . .32..
M. Malave
Progren sdis esign, resead rcdnahe velopmd etnneast tinf osg afety syeshtet mrofs
Korean next generation reactor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 27
Young Sang Choi, Byong Sup Kirn
The status of the ALPHA-Project . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 37
G. Yadigarog. GlVu,a ra. dJDi, r eedCi ae.Fcr,h a. rBdS, mit. ShG, iintay,
Th. Bandurski
PREDICTED PERFORMANCE AND ANALYSIS OF ADVANCED
WATER COOLED REACTOR DESIGNS (Ses)siIoIn
Evaluation of the design options for future power plants: Identification of the safety
related criteria and evaluation of the decay heat removal options . . . . . . . . .. 55
G.L. Fiorini
Postulated small break LOCA simulation in a CANDU type reactor with ECC
injection under natural circulation conditions . . . . . . . . . . . . . . . . . . . . .7.6
G. Bedrossian, S. Gersberg
A risk-based margins approach for passive system performance reliability analysis . 79
N.T. Saltos, A. El-Bassioni, C.P. Tzanos
Feasibility and efficiency studies of future PWR safety systems . . . . . . . . . . . .. 87
P. Aujollet
Risk reduction potential of jet condensers . . . . . . . . . . . . . . . . . . . . . . . . .. 95
A.W. Reinsch, T.G. Hook, K.I. Soplenkov, V.G. Selivanov,
V.V. Bredikhin, I.I. Shmal, Y. Filimonov, Y.N. Pavlenko
Diversified emergency core cooling in CANDU . . . . . . . . . . . . . . . . . . . . .. 105
P.J. Alien, N.J. Spinks
Mitigationf o total lossf o feedwater eventy b using safety depressurization system311 .
Y.M. Kwon, J.H. Song, S.Y. Lee, S.K. Lee
DESIGN AND ANALYSIS OF ADVANCED WATER COOLED REACTOR
SAFETY COMPONENTS AND SYSTEMS (Session ffl)
European pressurized water reactor configuration, functional requiremendntas
efficiency of the safety injection system . . . . . . . . . . . . . . . . . . . . . . . .. 125
F. Curca-Tivig, J.L. Gandrille
SWR-1000: the dimensioning of emergency condenser and passive
pressure pulse transmitters . . . . . . . . . . . . . . . . . . . . . . . . . . . . .7.31. ..
C. Palavecino
Design, fabrd icteanst fiatfoiounn lg l scale protr opotyafspse ive
cooling applications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 147
P. Giriba. lFMdia ,. gMOrirs. s l,RiFnizi z,o
RESULTF SOS AFETY-RELATED COMPONENTS/SYSTEMS TESTS
(Session IV) (Part 1)
Investigation pon assive decay heat removn aail dvanced water cooled 9r5e1ac .t o. .rs
F.J. Erbacher, X. Cheng, H.J. Neitzel
SPES-2, AP600 integral systems test results . . . . . . . . . . . . . . . . . . . . . . .. 173
L.E. Conway, R. Hundal
Experimn iennhtaearle ni ntlvyne satciogtuaatitoe dn pasdsiven injaectio n
depressurization system . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .78.1..
L. Mansani, L. Barucca, G.P. Gaspari
Design and testing of passive heat removal system with ejector-condenser . . . . .. 197
K.I. Soplenkov, V.G. Selivanov, Yu.N. Filimontsev, B.I. Nigmatulin,
V.V. Bredikhin, E.I. Trubkin, E.Z. Emeljanenko, A.W. Reinsch
An experimental study on the behaviour of a passive containment cooling system
using a small scale model . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 211
D. Saha, N.K. Maheshwari, D.K. Chandraker, V. Venkat Raj, A. Kakodkar
RESULTS OF SAFETY RELATED COMPONENTS/SYSTEMS TESTS
(Session IV) (Part 2)
Steam injector develop rmAoeLfnW t R's application . . . . . . . . . . . . .1.2.2. . . .
G. Cattador. LiG, albiat .LiM, azzocch .PiV, anin. VCi, avicchia
Tests on full-scale prototypical passive condensers for SBWR application . . . . . .. 233
P. Mason. AiA, chilli, P.P. Billi. gSB, ot. tGCi, attador. RiS, ilverii
Testing status of the Westinghouse AP600 . . . . . . . . . . . . . . . . . . . . . . . .. 245
E.J. Piplica, J.C. Butler
Testing for the AP-600 automatic depresurization system . . . . . . . . . . . . . . .. 263
T. Buete .LrC, onwa .PyIn, calcaterr. CaK, ropp
e ee hsfhtftT uefdcotyi e vehemtn efeorsgs enR c6yW0 0cBo/1n 0ed0he0tn sfoer
in the NOKO test facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 271
E.F. Hicken, H. Jaegers, A. Schaffrath
Experimental study of isolation condenser performances by piper-one apparatus . . . 279
R. Bovalini, F. D'Auria, G.M. Galassi, M. Mazzini
COMPUTER MODEL DEVELOPMENT AND VALIDATION (Session V)
Analysis of PACTEL passive safety injection tests with RELAP5 code . . . . . . .. 297
R. Munther, J. Vihavainen, J. Kouhia
Heat tn riaann- scofoetnr tainment heat exchann gneiar tural convection flow:
A vTEaeAlicd heahnttoi ofloon gy computational fluid dynamics code
CFDS-FLOW3D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 311
R. O'Mahoney, J.N. Lillington
ATHLET model ime dphertotevr mremoinefaf nhto iteoan t transfer coefficients
during condensatiof onv apon hir orizontal tubes . . . . . . . . . . . . . . . . 3.2.3 ..
E.F. Hicken, H. Jaegers, A. Schaffrath
RELAP5/MOD3 pre-test predictioe nhSt rosfP ES-2 "1C .L. break test S01613313 ...
. AAlembe .rCFtir, ep .GoGlir ,aziosi
Development and initial validation of fast-running simulator of PWRs: TRAP-2 . . . 341
.EBr. eLCgoam ,b. aMRrdici . ,oRSttoi r,di
Heat and mass transfer phenomena in innovative light water reactors . . . . . . . .. 353
W. Ambrosini, F. Oriolo, G. Fruttuoso, A. Manfredini,
F. Parozzi, M. Valisi
Application of the UMAE uncertainty method in assessing the design and the
safety of new generation reactors . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 365
F. D'Auria, G. Fruttuoso, G.M. Galassi, S. Galeazzi, F. Oriolo, L. Bella,
V. Cavicchia, E. Fiorino
F PLAOISRT TICIPANTS . . . . . . . . . . . . . . . . . . . . . . . . . . .1.8.3. . . . .
SUMMARY OF THE TECHNICAL COMMITTEE MEETING
The progress in design, R&D and testing of safety systems for advanced water cooled
reacs M taaocdworCdsn Trve easns nn eePiiddi acenzy a1a,M9 dIo9nt raan5gl iya nizneid
cooperation with ENEL SpA (ENEL), Ente per le Nuove Technologic, 1'Energia e 1'ambiente
(ENEA dnSa) ocieta Informazioni Esperienze Termoidrauliche (SIETe hTm). eetinsawg
1pa7artt itceyo niipndbwateend rtnt2 sca oft1driuoonnmn taraile o srganizat sifooanll sows:
Canada (1), Finland (2), France (8), Germany (5), India (1), Italy (37), Repubf loiKc orea
(3), Russia (5), Spain (1), Switzerland (1), United Kingdom (2), United States of America
(12), World Associatf iooNn uclear Plant Operators, WANO (1), IAEA (2). Thirty four
papers were presented and future needs and trends in the field were discussed.
Background
A main fof croues actor ded dsneigvane lopmene ti hnedft funosrittrs ialized countries
is on large size water cooled reactor units, with power outputs well above 1000 MW(e),
typically aiming ta achieving certain improvements over existing designs.e hT alterationsdna
modificatioa n sostp ecific desige rnag enerally keps ats mas lalp ossible taking maximum
advantage of successful proven design features and components while taking into account
feedbackf o experience from licensing, construction, commissionind gnao peratioehtn fo
water cooled reactor plants currentlyn i operatione hT.d esign improvements spana wide
range but still enhanced safety, increased reliability, more user-friendly systems, and better
economics represent rather common denomw idnenea esthoti grrosfn s.
New designs - designs that have not yet been built or operated - are generally called
advanced designs. If they do not deviate too much from their predecessors, they are
designated evolutionary designs; the designers have retained many proven features of today's
plant design, and the evolutionary plant designs therefore require at most engineering, and,
possibly, confirmatory testing of some components and systems prior to commercial
deployment.
Some evolutionary large size LWR designs are currently under construction, while
others are in varying phases of design and regulatory review. The N4 model, a 1400 MW(e)
PWR, which is under construction in France, derives directly from the standardized P4 series
of 1300 MWe Bh(Trei)t.i sh Sizewell-B a1, 250 MW(e) PWRs ai, nother exanma pfole
evolutionary designn a -e volutioe hnt Wfo PSS designf o Westinghouse. Other examples
of large advanced, evolutionary desige nWht esra estinghouse-Mitsubishi advanced pressurized
water reactor APa W1(3R5 0 B CMoBmWbA(ues)t io PenW hERntg) ,ineering System
e aW13hW(00Et MR -W+1f0(0eoe 0R0) Puh sW8sRiaRtn ) a ,1VW0-(0309 2MPW(e )
type), and the General Electric-Hitachi-Toshiba Advanced Boiling Water Reactor ABWR (a
1350 MW(e) BWRn )It. his co enbn tyeoamxte ttid, th owaAtt BWR unie trasu nder
t Kaashiw aczon -Janakspit a riKuncatriio wna (No -.w 6it/h7 g)rid connections scheduled
for d 11d 9nt9h9na9a6a 7t c,oo nAswtPruWtc ftRioo un e ns Tpihitlsas tun rtnuaegda site
in Japan.
Framatome and Siemens have established a joint company, Nuclear Power
International, which is developing a new advanced large PWR of 1500 MW(e) (gross) with
enhanced safetyd tfheneaytau o r tidhneriaetse t e,vvnFn eihr deeawntecdh yjobintl y
German safety authorities. This procedure will provide strong motivation for the practical
harmone ihszataf tefitooyn requio rmwematj eofnro ts countries, which could laetber
enlarga b eordto ader basis. Siemens ais lso, together with German utilities, engeahgt endi
developmen ana fodt vancR edWdBe signe hSt, WR-1000, which will incorporatea number
of passive safety features, for initiation of safety functions, for residual heat removal and for
containment heat removal. In Sweden, ABB Atom, with involvement of the utility
Teollisuuden Voima Oy (TVO) of Finland, is developing the BWR 90 as an upgraded version
of the BWRs of the BWR 75 version operating in both countries.
Smaller advanced LWRs are also being developed in a number of countries, in most
cases with a great emphasis on utilization of passive safety systems and inherent safety
featuo rwteyTsp. ical examplen tsi his con ethAet exdratv anced PassR i(WvAPe P-600fo)
Westinghouse and the Simplified BWR of General Electric - the mid-size passive units (units
in 006 eht MW(e) rangeS U) eht foA LWR programme.e hT development fo both these
designs has been governed by a key guideline: new features should need no more than
engineering and confirmatory testing before commercial deployment; they must not lead to
a requirement of building and operating a prototype or demonstration plant.
An important programme in the development of advanced light water reactors was
initiated in 1984 by the Electric Power Research Institute (EPRI), an organization of US
utilities, with financial support from the US Department of Energy, and participation of US
nuclear plant designers. Several foreign utilities have also participated in, and contributed
fe uphnrtod ,gionrte gap ha mrtp o safmAgorrte a. mmo getu, e iAhdteL WR desdingan
development, utility requirements were established for large BWRs and PWRs having power
ratinf goasb out 1200 M romfWi dd(-nesai)z, ed BWd PnRWas Rs having power ratinfgos
about 600 MW(e). In an important related development, a major step forward in licensing
of future plans artwes ached wie trhhta tificae tEhito nfone rgy Pof ol1w itcc9eAny9 e2hT.
licensing process allows nuclear plant desigo nseutrbs mS NiUtu tchl eeeairrh dte soigtns
Regulatory CommisS sNUioR(n rCodfe) sign certification. Onca ed esigs cin ertifeiehdt,
standardized units ewcboilm l mercially a un o otfdiarfldeicna trepy aer lda ,nt confident that
generic design and safety issues have been resolved. The licensing process will allow the
power company to request a combined license to build and operate a new plant, and as long
as the plant is built to pre-approved specifications, the company can start up the plant when
construction is complete, assuming no new safety issues have emerged. In 1994, the two
large evolutionary plants which have resulted from the U S programme, ABB-Combustion
Engineering's System 80+ and General Electric's (GE's) ABWR, received Final Design
Approvae lhlt, ast step before design certification, frS oUN mehtR o wstC mehT.a ll0e06r
MW(e) plants, Westinghouse's AP-600 and GE's Simplified BWR, are expected to receive
Final Design Approval in 1996 and 1997 respectively. Today, completion of design
certific raaotdiofvn anced light water reacto oatrsss ufreo a vdanileab eif lAhoitLyt WyRbs
the decade is a top priority of the Advanced Reactor Programme of the US Department of
Energy.
An adaption of the AP600 and SBWR designs in order to meet the European Utility
a t heeil genrche Rote onr rheimefcqte teud p ei dros tewuimnnede arnetr s prognreis s
o prwogrtae mneraEd mmaEhuenSer sTdoBa pWree .sRPp.ePctiEvely
Ine ht Russian Federation, design worke ht no evolutionary V-392,n a upgraded
versie ohWt nfo WER-1000s abh, een startedd ana,n other design versions ib eing developed
in cooperation with Finle ahRnTuds. sian Federatios ian lso developin naegv olutionary
10