ENC '94: International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 1994,2 Poster session papers
Gespeichert in:
| Körperschaft: | |
|---|---|
| Format: | Tagungsbericht Buch |
| Sprache: | English |
| Veröffentlicht: |
Bern
ENS
1994
|
| Online-Zugang: | Inhaltsverzeichnis |
| Beschreibung: | 596 S. graph. Darst. |
| ISBN: | 3952069108 |
Internformat
MARC
| LEADER | 00000nam a2200000zcc4500 | ||
|---|---|---|---|
| 001 | BV022074818 | ||
| 003 | DE-604 | ||
| 005 | 20060314000000.0 | ||
| 007 | t | ||
| 008 | 960614s1994 d||| |||| 10||| eng d | ||
| 020 | |a 3952069108 |9 3-9520691-0-8 | ||
| 035 | |a (OCoLC)37573264 | ||
| 035 | |a (DE-599)BVBBV022074818 | ||
| 040 | |a DE-604 |b ger | ||
| 041 | 0 | |a eng | |
| 049 | |a DE-706 | ||
| 111 | 2 | |a ENC |d 1994 |c Lyon |j Verfasser |0 (DE-588)2160079-X |4 aut | |
| 245 | 1 | 0 | |a ENC '94 |b International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 |n 1994,2 |p Poster session papers |c organized by the European Nuclear Society ... |
| 264 | 1 | |a Bern |b ENS |c 1994 | |
| 300 | |a 596 S. |b graph. Darst. | ||
| 336 | |b txt |2 rdacontent | ||
| 337 | |b n |2 rdamedia | ||
| 338 | |b nc |2 rdacarrier | ||
| 773 | 0 | 8 | |w (DE-604)BV021856588 |g 1994,2 |
| 856 | 4 | 2 | |m GBV Datenaustausch |q application/pdf |u http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=015289616&sequence=000001&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA |3 Inhaltsverzeichnis |
| 999 | |a oai:aleph.bib-bvb.de:BVB01-015289616 | ||
Datensatz im Suchindex
| _version_ | 1804136050467012608 |
|---|---|
| adam_text | ENC 94 INTERNATIONA! NUCLEAR CONGRESS ATOMS FOR ENERGY A DIALOGUE WITH
THE INDUSTRY S YOUNG GENERATION ON NUCLEAR S FUTURE EUREXPO, LYON
OCTOBER 2-6, 1994 ORGANIZED BY THE EUROPEAN NUCLEAR SOCIETY, IN
COLLABORATION WITH THE AMERICAN NUCLEAR SOCIETY AND FORATOM CO-SPONSORED
BY: CANADIAN NUCLEAR SOCIETY, CHINESE NUCLEAR SOCIETY, JAPAN ATOMIC
INDUSTRIAL FORUM AND KOREA ATOMIC INDUSTRIAL FORUM VOLUME II POSTER
SESSION PAPERS UB/T1B HANNOVER 89 TABLE OF CONTENTS FOR INVITED PLENARY
SESSION PAPERS SEE VOLUME I TOP = THREE BEST PAPER PER SESSION AWARD
POSTER SESSION 1 THE NEED FOR NUCLEAR ENERGY IN DIFFERENT PARTS OF THE
WORLD 1.01 THE TEN COMMANDMENTS OF UTILITY PLANNING (OR THE CONTINUED
NEED FOR 1 TOP NUCLEAR ENERGY IN THE UNITED STATES, BYMARC S. GERVALS
(NUCLEAR ENERGY INSTITUTE, WASHINGTON, D.C. USA) 1.02 FUNDAMENTAL
REQUIREMENTS FOR ESTABLISHMENT OF NUCLEARPOWER FOR S THE DEVELOPING
COUNTRIES, BY K. K. U (DA-YEN INSTITUTE OF TECHNOLOGY, CHANGHWA TAIWAN)
1.03 THE QUEST FOR ENERGY: NUCLEAR ENERGY OUTLOOK IN TURKEY, BY 9 TOP
KENAN CLNLU (THE UNIVERSITY OF TEXAS IN AUSTIN, TEXAS USA) AND B. NAZLM
BAYRAKTAR (TURKISH ATOMIC ENERGY AUTHORITY, ANKARATURKEY) 1.04 THE
COMPETITIVENESS OF EVOLUTIONARY NUCLEAR PLANTS IN THE UNITED STATES, 13
BY BONN JAMES MACY (NUS, WASHINGTON D.C. USA) 1.05 PRESENT STATUS AND
FUTURE ROLE OF RESEARCH NUCLEAR REACTORS IN 17 INSTITUTE OF NUCLEAR
SCIENCES VINCA, BY MILAN PESLC AND STEFAN CUPAC (INSTITUTE OF NUCLEAR
SCIENCES VINCA, BELGRADE YU) 1.06 COMPARINGTHE ECONOMICS OF NUCLEAR
POWER WITH ALTERNATIVE ELECTRICITY 21 GENERATION OPTIONS IN FINLAND, BY
ANTTL LEHTLIA (TECHNICAL RESEARCH CENTRE OF FINLAND (VTT), ESPOO FIN)
1.07 WOULD HTR BE SUITABLE FOR APPLICATION IN THE NETHERLANDS? BY 25
ALLKL I. VAN HEEK (NETHERLANDS ENERGY FOUNDATION ECN, PETTEN NL) 1.08
CIVIL UTILIZATION OF NUCLEARWEAPON MATERIAL, BY V.M. MUROGOV, M.F.
TROYANOV, 29 V.G. ILUNLN, V.S. KAGRAMANYAN, N.S. RABOTNOV AND V.YA.
RUDNEVA (INSTITUTE OF PHYSICS AND POWER ENGINEERING, OBNINSK RUSSIA)
1.09 CONDITIONS OF RESTARTING THE DEVELOPMENT OF NUCLEARPOWER IN POLAND,
33 BYJACEK MARECKL, KAZLMLERZ T. KOSMOWSKL AND RYSZARD FRYDRYK
(TECHNICAL UNIVERSITY OF GDANSK, GDANSK PL) 1.10 ST. PETERSBURG
(LENINGRAD) NPP S REGION RADLOECOLOGLCAL STATE ESTIMATION, 37 BY LD.
BLLNOVA (V.G. KHLOPLN RADIUM INSTITUTE, ST. PETERSBURG RUSSIA) 1.11 ST.
PETERSBURG (LENINGRAD) NUCLEAR POWER PLANT: NONRADIOACTIVE IMPACT 40 ON
AQUATIC ENVIRONMENT, BY LM. ZIMLNA (V.G. KHLOPLN RADIUM INSTITUTE, ST.
PETERSBURG RUSSIA) 1.12 PERSPECTIVES OF APPLICATION OF LOW-POWER NUCLEAR
PLANTS IN SAKHA 43 REPUBLIC (YAKUTIA), BY A.YU. ORLOV (THE INSTITUTE OF
PHYSICAL- TECHNICAL PROBLEMS OF THE NORTH OF THE SIBERIAN DIVISION OF
THE RUSSIAN ACADEMY OF SCIENCES, YAKUTSK RUSSIA) 1.13 ENERGY ORIENTED
RESEARCH AT ACCELERATOR LABORATORY IN CROATIA, 47 BY PETARTOMAS (RUDER
BOSKOVLC INSTITUTE, ZAGREB CROATIA) 1.14 SMALL POWER NUCLEAR ENERGY
SOURCES. CONVERSION POTENTIAL. STATUS 51 TOP AND PERSPECTIVES, BY LV.
GUREYEVA, YU. K. PANOV AND E.V. AKHMEDJAYEVA (OKB MECHANICAL
ENGINEERING, NLZNY NOVGOROD RUSSIA) 1.15 AIR POLLUTION OF ATMOSPHERE
FROM DIFFERENT ENERGY SOURCES, BY 59 D. ANTIC, M. SOKCLC-KOSTLC, T.
PAPLC (INSTITUTE OF NUCLEAR SCIENCES VINCA , NUCLEAR ENGINEERING
LABORATORY, BELGRADE YU) AND B. TELENTA (FEDERAL HYDROMETEOROLOGLCAL
INSTITUTE, BELGRADE YU) 1.16 CURRENT ECONOMIC SITUATION AND ESTIMATED
FUTURE TRENDS OF THE 63 ELECTRICITY GENERATION OPTIONS IN BELGIUM, BY G.
FREDERICK, J.P. GLLLON AND J. DELVOYE (BELGATOM, BRUSSELS B) 1.17 STATUS
OF ELECTRICITY SUPPLY IN REUNIFIED GERMANY, BY DIETERFAUDE 67 (KARLSRUHE
NUCLEAR RESEARCH CENTRE, KARLSRUHE D) POSTER SESSION 2 SAFETY OF
OPERATING NUCLEAR POWER PLANTS 2.01 CONTAINMENT PROTECTION AGAINST
HYDROGEN HAZARDS, BY FERRUCCLO FERRONL 71 (ELECROWATT ENGINEERING
SERVICES LTD., ZURICH CH) PETER COLLINS (SULZER CHEMTECH LTD.,
WLNTERTHUR CH) AND LOTHAR SCHLEL (SULZER THERMTEC LTD., WLNTERTHURCH)
2.02 NEW CONCEPT OF THE ENVIRONMENTAL PROTECTION FROM RADLOAEROSOLS OF
75 CESIUM AND IODINE DURING ACCIDENTS AT NUCLEAR POWER PLANTS, BY
NIKOLAI MLKHEEV, SERGEI KULYUKHLN, ALIA KAMENSKAYA, IGOR RUMER, MIKHAIL
KAZAKEVLCH AND VLTALIL NOVICHENKO (INSTITUTE OF PHYSICAL CHEMISTRY,
RUSSIAN ACADEMY OF SCIENCES, MOSCOW RUSSIA) 2.03 ANALYSIS OF EXTERNAL
PRESSURIZED THERMAL SHOCK, BY ALPO NEUVONEN, 79 PENTTL RAJAMAKL AND OIL!
KYMALALNEN (IVO INTERNATIONAL UD, VANTAA FIN) 2.04 THE SAFE OPERATION
OFLMFBR S IN SPITE OF THESODIUM FIRE PROBLEMS, BY 83 W. CHERDRON
(KARLSRUHE NUCLEARRESEARCH CENTER, KARLSRUHE D) 2.05 EXPERIMENTS ON THE
CIRCULATIONFLOW RESONANCE IN NATURAL CIRCULATION 87 COOLED BWRS, BY
A.J.C. STEKELENBURG AND T.H.J.J. VAN DER HAGEN (DELFT UNIVERSITY OF
TECHNOLOGY, DELFT NL) 2.06 EFFECTIVENESS OF ECCS DURING LOSS OF COOLANT
ACCIDENT, BY ADREJ PROSEK, 91 BORUT MAVKO AND ANDREJ STRITAR (UNIVERSITY
OF LJUBLJANA, INSTITUTE JOSEF STEFAN , LJUBLJANA SLO) 2.07 THE SAFETY
OF OPERATING NUCLEAR POWER PLANTS: EVALUATION OF EXTERNAL 95 EVENTS, BY
H.P. BERG, R. G8RTZAND TH. SCHAEFER, BUNDESAMT FUR STRAHLENSCHUTZ,
SALZGLTTER D) 2.08 SURVEY OF FRENCH PWR CORE SEISMIC ANALYSIS, BY
JEAN-CLAUDE LEROUX 99 AND JEAN RIGAUDEAU (FRAMATOME NUCLEAR FUEL, LYON
F) 2.09 STUDY OF CORE RESPONSE IN REACTIVITY ACCIDENTS DUE TO LOCAL
DILUTION 105 OF BORIC ACID CONCENTRATION, BY PERTTL SILTANEN, MARTTI
ANTLLA (IVO INTERNATIONAL LTD, VANTAA FIN) AND RIITTA KYRKI-RAJAMAKL
(VTT ENERGY, ESPOO FIN) 2.10 THE HARMONLSATLON OF METHODS FOR EVALUATING
THE RADIOLOGICAL 112 TOP CONSEQUENCES OF ACCIDENTS AT PWRS, BY LM.C.
DUTTON, C. SMEDLEY (NNC LTD, KNUTSFORD GB) AND W. ESSLER (CEC, BRUSSELS
B) 2.11 RODOS: REAL-TIME ON-LINE DECISION SUPPORT SYSTEM FOR OFF-SITE
116 EMERGENCY MANAGEMENT, BY G. BENZ, M. RAFAT (D.T.I. DR. TRLPPE
INGENLEURGESELLSCHAFT M.B.H, KARLSRUHE D), J. EHRHARDT, D. FAUDE, F.
FISCHER, A. LORENZ, J. PASLER-SAUER, T. SCHLCHTEL, O. SCHCILE AND C.
STELNHAUER (KARLSRUHE NUCLEAR RESEARCH CENTRE, KARLSRUHE D) 2.12
IMPROVED MANAGEMENT OF PRIMARY TO SECONDARY LEAKS AT LOVIISA 120
NUCLEARPOWER PLANT, BY ULLA VUORLO (IVO INTERNATIONAL LTD., VANTAA FIN)
AND ALPO SAVIKOSKL (IMATRAN VOLMA LTD., LOVLLSA FIN) 2.13 SEVERE
ACCIDENT MANAGEMENT GUIDANCE FOR PWRS, BY R.P. PRIOR 124 (WESTLNGHOUSE
ENERGY SYSTEMS EUROPE, BRUSSELS B), R.J. LUTZ, D.K. OHKAWA (WESTLNGHOUSE
ELECTRIC CORPORATION, PITTSBURGH USA) AND J.M. BERMEJO (WESTLNGHOUSE
SISTEMAS ENERGETLCOS ESPANA, MADRID E) 2.14 CATALYTIC RECOMBLNERS FOR
SEVERE ACCIDENT HYDROGEN, BY G.W, KOROLL, 129 W.A. DEWLT, D.W.P. LAU
(AECL RESEARCH, WHLTESHELL LABORATORIES, PLNAWA MANITOBA CAN) AND W.R.C.
GRAHAM (AECL RESEARCH, CHALK RIVER LABORATORIES, CHALK RIVER ONTARIO
CAN) 2.15 AGEING MANAGEMENT THROUGH MAINTENANCE AT TARAPUR, BY SUNIL
GADGLL 132 (TARAPUR ATOMIC POWER STATION, THANE INDIA) 2.16 REMAINING
LIFETIME MANAGEMENT AS A RESPONSE TO THE GROWING DEMANDS 136 ON SAFETY,
ECONOMY AND LIFETIME OF NPPS, BY ESTHER PATOP AND FERNANDO HEVLA
(EMPRESARLOS AGRUPADOS, MADRID E) 2.17 SAFETY AND AVAILABILITY, BY D.
BERQUEZ (FRAMATOME, PARIS F) AND 140 M. MAXANT (EDF, PARIS F) 2.18 CRACK
RISK ASSESSMENT COMPUTATION - APPLICATION TO DEFECT DIAGNOSIS 144 AND
PREVENTIVE MAINTENANCE, BY F. MATTEL, J. HELLOTAND A. LEFRANCOIS
(FRAMATOME, PARIS LA DEFENSE F) 2.19 AN INTEGRATED APPROACH TO LIFE
CYCLE MANAGEMENT, BY MAHENDRA VERMAUT 150 (WESTLNGHOUSE ELECTRIC
CORPORATION, BRUSSELS B) AND MARK KAUSHANSKY (WESTLNGHOUSE ELECTRIC
CORPORATION, PITTSBURGH USA) 2.20 MAINTENANCE COST SAVINGS -SNUBBER
ELIMINATION WITH LIMIT STOPS, BY 156 ROBERT L CLOUD (ROBERT L CLOUD AND
ASSOCIATES, INC., BERKELEY USA), PHILIPPE MONETTE AND ROBERT BALTUS
(WESTLNGHOUSE ELECTRIC CORPORATION, BRUSSELS B) 2.21 EXTENDED LIFETIME
FOR THE REACTOR VESSEL USING LOW LEAKAGE LOADING 162 PATTERN, BY FREDRLK
JOHANSSON (VATTENFALL FUEL, VALLLNGBY S) 2.22 EXTRAPOLATION METHOD FOR
INCORE-EXCORE NUCLEAR INSTRUMENTATION CALIBRATION 165 AT REACTOR
STARTUP, BY MASASHI TAKENO (JAPAN ATOMIC POWERCOMPANY, TSURUGA CITY,
JAPAN), YOICHLRO SHLMASU AND HAJIME YASUL (MITSUBISHI ATOMIC POWER
INDUSTRIES INC., TOKYO JAPAN) 2.23 BACKFITTING A DIGITAL CLASS IE
SYSTEM, BY STEFAN BORLLN AND 169 ANDERS BACK (ABB ATOM, VASTERAS S) 2.24
BENEFITS WITH ABB S INTEGRATED REACTOR AND TURBINE CONTROLLER CONCEPT,
173 BY EINAR ZETTERGREN, MARTEN AKESSON AND ANDERS RLNGDAHL (ABB ATOM,
VASTERAS S) 2.25 FLOS *A NEW MONITORING SYSTEM FOR LEAK DETECTION AND
LOCATION, BY 177 TOP V. STRELCHER AND P. JAX (SIEMENS AG, ERLANGEN D)
2.26 AN INTEGRATED DIGITAL CONTROL SYSTEM FOR NEW PWRS IN KOREA, BY 181
LL-NAM CHOE (KOREA POWER ENGINEERING CO. INC., SEOUL KOREA) 2.27 IN-SITU
RESPONSE TIME TESTING OF TEMPERATURE AND PRESSURE SENSORS IN 185 NUCLEAR
POWER PLANTS, BY H.M. HASHEMIAN (ANALYSISAND MEASUREMENT SERVICES
CORPORATION, KNOXVLLLE USA) 2.28 NEW METHODS FOR ON-LINE TESTING OF
CALIBRATION OF TEMPERATURE AND 189 PRESSURE SENSORS IN NUCLEARPOWER
PLANTS, BY H.M. HASHEMIAN (ANALYSIS AND MEASUREMENT SERVICES
CORPORATION, KNOXVLLLE USA) 2.29 REACTOR VESSEL HEAD ADAPTER INSPECTION
AND REPAIR, BY A. THOMAS 193 (FRAMATOME, LYON F) 2.30 UTS UNIVERSAL
TESTING SWORD, BY PER SJ&BERG (ABB TEKNLSKA 197 RFLNTGENCENTRALEN AB
(TRC), TFIBY S) 2.31 UNISESAM: NEXT GENERATION RPV ID-INSPECTION TOOL,
BY LARS DRUGGE 201 (ABB TEKNLSKA RDNTGENCENTRALEN AB (TRC), TABY S) 2.32
PWR BOTTOM NOZZLE INSPECTION, BY MARLKAWESTMAN (ABB TEKNLSKA 205
RFLNTGENCENTRALEN AB (TRC), TABY S) 2.33 LEADING EDGE SAFETY SHUTDOWN
SYSTEM, BY ALLSTALR SMITH AND KEITH 208 MCMINN (NNC LTD, KNUTSFORD GB)
2.34 CONTROL ROD DRIVE MONITORING SYSTEM, BY JIRI USKA, KAREL DVORAK 211
AND FRANTLSEK DALLK (SKODA, PLZEN CZ) 2.35 INTRODUCTION OF GADOLINIUM AS
A PWR INTEGRAL BURNABLE POISON IN THE 214 SPANISH NUCLEAR INDUSTRY, BY
F. MERINO AND M.A. MONTES (ENUSA, MADRID E) 2.36 PWR FUEL IN JAPAN -
PROGRESS AND FUTURE TRENDS, BY MLTSUHLRO YOKOTA 218 (KANSAL ELECTRIC
POWER CO., OSAKA JAPAN), YOSHLAKI KONDO (NUCLEAR DEVELOPMENT COMPANY
JAPAN) AND SADAAKI ABETA (MITSUBISHI HEAVY INDUSTRIES, YOKOHAMA JAPAN)
2.37 EXPERIMENTALWER SAFETY STUDIES IN FINLAND, BY PEKKA RAUSSL, RELJO
222 MUNTHER, HELKKI KAIL! (LAPPEENRANTA UNIVERSITY OF TECHNOLOGY,
LAPPEENRANTA FIN), JYRKI KOUHLA AND MARKKU PUUSTLNEN (VTT ENERGY,
LAPPEENRANTA FIN) 2.38 RADIOACTIVE CONTAMINATION OF THE ENVIRONMENT IN
THE AREAS OF NPPS 226 WITH REACTORS OF THEWER AND RBMK TYPE, BY I.I.
KRYSHEV (SCIENTIFIC PRODUCTION ASSOCIATIONTYPHOON , OBNINSK RUSSIA) 2.39
SAFETY IMPROVEMENT OFWER - THE ENAC CONTRIBUTION, BY D. TAYLOR 230
(ENAC, BRUSSELS B) AND E.L INGHAM (NNC LTD, KNUTSFORD GB) 2.40 L&C
REPLACEMENTS FORWER TYPE 440/V213 NPPS, BY A.F. PARSONS 234 AND D.P.D.
WHLTWORTH (NNC LTD, KNUTSFORD GB) 2.41 SYSTEM FOR EARLY EMERGENCY
PROGNOSIS AND RESPONSE CENTERS, BY 237 YU.L TSOGLLN, V.I. BORLSENKO,
I.A. KLLMENKO, V.S. LYUBARSKY AND N.M. SLDORUCK (INSTITUTE FOR NUCLEAR
RESEARCH, NATIONAL ACADEMY OF SCIENCE OF UKRAINE, KIEV UKRAINE) 2.42 THE
DUKOVANY NPP * THE PAST, THE PRESENTAND PROSPECTS OF FURTHER 241
OPERATION, BY ZDENEK LLNHART AND MIROSLAV TRNKA, (NPP DUKOVANY, DUKOVANY
CZ) 2.43 EXPERIMENTS ON THE DETERMINATION OFWERZ-M-10 RESEARCH REACTOR
POWER 245 BY N-16 ACTIVITY MONITORING, BY I. BENKOVLCS (KFKI MTA,
BUDAPEST H), K. ERDELYL, I. ALMASL AND I. SZENDRD (MLCROVACUUM LTD.,
BUDAPEST H) 2.44 THE MAIN PRINCIPLES OF TECHNICAL SECURITY SYSTEMS
DEVELOPMENT FOR 247 RUSSIAN POWER PLANTS PHYSICAL PROTECTION, BY
ALEXANDER V. IZMALLOV (SPECIAL SCIENTIFIC & PRODUCTION STATE ENTERPRISE
ELERON , MOSCOW RUSSIA) 2.45 RINGHAIS NPP, UNIT 1 DESIGN BASES RENEWAL
PROGRAMME, BY MARIA HENRIKSSON, 251 JAN LADEBORN AND CARINA KARLSSON
(VATTENFALL AB, RLNGHALS NPP, VSROBACKA S) 2.46 INNOVATIVE SAFETY
FEATURES OF THE N4 PLANT DESIGN, BY D. LANGE 254 TOP (FRAMATOME, PARIS
F) AND B. VLDAL (EDF SEPTEN, VLLLEURBANNE F) 2.47 EMDISY - TOOL TO
SUPPORT OPERATOR DURING EMERGENCY, BY IGOR SALAMUN, 258 BORUT MAVKO AND
ANDREJ STRLTAR (UNIVERSITY OF LJUBLJANA, INSTITUTE JOSEF STEFAN ,
LJUBLJANA SLO) 2.48 DIMOS: THE WAY TO REALIZE HARMONY BETWEEN THE
OPERATOR AND THE NUCLEAR 262 PROCESS, BY GEERT UYTTERHOEVEN, MICHEL DE
VLAMINCK AND BERNARD GILLLOT (BELGATOM, BRUSSELS B) 2.49 RADIATION
PROTECTION EXPERIENCE IN NONSTANDARD OPERATION OF FIRST 267 YUGOSLAV
REACTOR RB, BY M.M NINKOVIC AND J.J. RALCEVLC (INSTITUTE OF NUCLEAR
SCIENCES VINCA, BELGRADE YU) 2.50 ROOT CAUSE ANALYSIS, BY OLLL NEVANDER
(IVO INTERNATIONAL LTD, VANTAA FIN) 271 AND JARL SNELLMAN (IVO LOVLLSA
NPP, LOVLISA FIN) 2.51 A PLANT INFORMATION SYSTEM IN LINE WITH L&C
UPGRADE, BY PASCAL ANCLON 275 (WESTLNGHOUSE ELECTRIC CORPORATION,
BRUSSELS B) 2.52 FEEDBACK FROM EXPERIENCE GAINED WITH STEAM GENERATORS
REPLACEMENT 279 AT DOEL 3 NPP (BELGIUM), BY MARC LEPLECE AND FRANCLNE
VERMLNNEN (BELGATOM, BRUSSELS B) 2.53 TRAINING AND QUALITY, BY NATHALIE
IDRLSSL (FRAMATOME, PARIS LA DEFENCE F) 286 2.54 TECHNICAL AND
ECONOMICAL BENEFITS FROM RISK- AND PREDICTION ANALYSES AT 290 AGEING
MANAGEMENT PROGRAM, BY S6REN STRLDSBERG (ABB ATOM, VASTERAS S) POSTER
SESSION 3 BACK-END OF THE FUEL CYCLE: RECYCLING AND DIRECT STORAGE OF
FUEL ELEMENTS 3.01 DESIGNAND ERECTION OF THE PILOT PLANT FOR SPENT FUEL
CONDITIONING, 294 BY M. WINTER, I. HLLDEBRANDT AND J. BALER (NOELL GMBH,
WURZBURG D) 3.02 THE BEHAVIOUR OF NP IN A NITRIC ACID U-PU PARTITION
PROCESS, 298 BY YASUO HLROSE (HITACHI WORKS, HITACHI JAPAN), YOLCHL
TAKASHLMA AND YASUHLSA IKEDA (INSTITUTE OF RESEARCH AND INNOVATION,TOKYO
JAPAN) 3.03 SPENT FUELS CONDITIONING AND IRRADIATED NUCLEAR FUEL
ELEMENTS 303 EXAMINATION: THE STAR FACILITYAND ITS PROCESSES, BY F.
BOUSSARD, R. HULLLERY (CEA, CADARACHE F), J.L AVERSENG AND J.P.
SERPANTLE (FRAMATOME/NOVATOME, LYON F) 3.04 TREATMENT OF SPENT
GRANULATED NATURAL SORBENTS FOR FURTHER SAFE 307 HANDLING AND STORAGE,
BY S.YU. SAYENKO, R.V. TARASOV AND V.P. KANTSEDAL (NATIONAL SCIENCE
CENTRE KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY (KIPT), KHARKOV
UKRAINE) 3.05 EFFECTIVE IMPLEMENTATION AND ASSESSMENT OF THE SAFETY AT
THE UP 3 311 REPROCESSING PLANT, BY G. DUBOIS (COGEMA, VELTZY F) 3.06
TREATMENT OF RADIOACTIVE EFFLUENTS USING ENHANCED ULTRAFILTRATION, BY
316 R. LIBERGE, C. REDONNET (SGN, SALNT-QUENTLN-EN-YVELLNES F), P. HURON
AND J.-M. FERNANDEZ (COGEMA, LA HAGUE F) 3.07 ELECTROGENERATED AG II FOR
RECOVERY OF PU02 FROM WASTE, BY M.-H. MOULLNEY, 321 F.-J. PONCELET, P.
MIQUEL (SGN, SALNT-QUENTLN-EN-YVELLNES F), V. DECOBERT (COGEMA, VELIZY
F) AND M. LECOMTE (CEA, SACLAY F) 3.08 FIBER REINFORCED CONCRETE
CONTAINERS, BY A. VERDIER (SOGEFLBRE, SAINT- 326 QUENTLN-EN-YVELLNES F)
AND J.-C. DELRLEU (SGN, SALNT-QUENTLN-EN-YVELLNES F) 3.09 ALPHA WASTE
INCINERATION, BY J.-PH. DUREC, E. DE SAULLEU (SGN, SAINT- 332
QUENTLN-EN-YVELLNES F) AND J. LANNAUD (CEA, VALDUC F) 3.10 OPTIMIZATION
OF WASTE MANAGEMENT AT THE LA HAGUE UP3 PLANT, BY 337 C. BERNARD (SGN,
SALNT-QUENTLN-EN-YVELLNES F) AND P. LEDERMANN (COGEMA, LA HAGUE F) 3.11
APPLICATION OF INDUCTIVELY COUPLED PLASMA/EMISSION SPECTROMETRY TO 341
LABORATORY ANALYSES, BY J. BESNTER (COGEMA, LA HAGUE F), L BROMET AND J.
HUNI (SGN, SAINT-QUENTLN-EN-YVELINES F) 3.12 ADVANCED REPROSESSING OF
SPENT NUCLEAR FUELS, BY J.P. GLATZ, Y. MOR ITA, 345 C. SONG AND L KOCH
(EUROPEAN COMMISSION, J.R.C., EUROPEAN INSTITUTE FOR TRANSURANIUM
ELEMENTS, KARLSRUHE D) 3.13 IMPROVEMENTS IN FUEL MANUFACTURING
EQUIPMENTAND PROCEDURES FOR INDUSTRIAL 349 PRODUCTION OF REPROCESSED
URANIUM FUEL RELOADS, BY JEAN HENCKES, CHRISTIAN DELEVALLEE AND PHILIPPE
DEWEZ (FBFC, ROMANS F) 3.14 INCREASE OF THE QUANTITY OF PLUTONIUM
RECYCLED WITHIN FRENCH 900 MWE 353 PLANTS - MOX 95 FEASIBILITY STUDIES,
BY ALEXIS MARLNCIC, FRANGOIS-YVES GUENA (FRAMATOME, PARIS LA DEFENSE F)
AND XAVIER THLBAULT (EDF/SEPTEN, VILLEURBANNE F) 3.15 A COHERENT
STRATEGY FOR PLUTONIUM AND ACTINLDE RECYCLING, BY J. TOMMASI, 358 J.C.
GARNLER (CEA - C.E. CADARACHE, ST-PAUI-LEZ-DURANCE F) AND D. VERRLER
(FRAMATOME/NOVATOME, LYON F) 3.16 PWR S POTENTIALITIES FOR PLUTONIUM
RECYCLING AND MINOR ACTINIDES BURNING, 362 BY M. DELPECH, R. GLRIEUD
(CEA DER/SPRC - C.E. CADARACHE, ST-PAUWEZ- DURANCE F) AND G. MANENT (CEA
DER/SIS - C.E. CADARACHE, ST-PAUMEZ- DURANCE F) 3.17 MOX FUEL IN PWR S:
STATUS AND OUTLOOK, BY MICHEL DELOR, FRANCK OBADIA 367 TOP (FRAMATOME,
LYON F), JEAN-LUC GUILLET AND CLAUDE GOLLNELLL (COGEMA, VETIZY F) 3.18
RECYCLING OF ACTINIDESAND FISSION PRODUCTS, THE DUTCH RAS RESEARCH 375
PROGRAMME, BY K. ABRAHAMS, E.H.P. CORDFUNKE, W.M.P. FRANKEN, H.
GRUPPELAAR, J.LKIOOSTERMAN, R.J.M. KONLNGS AND A.M. VERSTEEGH
(NETHERLANDS ENERGY RESEARCH FOUNDATION ECN, PETTEN NL) 3.19 SVEA-96
DESIGNS FOR BWR MOX ASSEMBLIES, BY LARS PAULSSON (ABB ATOM, 379 VASTERAS
S) AND JOSEPH AFONSO (ELEKTROWATT ENGINEERING SERVICES LTD, ZURICH CH)
3.20 SENSITIVITY OF THE SUPPORT RATIO IN FAST REACTOR INCINERATION
CALCULATIONS, 384 BY H.W. WIESE AND B. KRLEG (KARLSRUHE NUCLEAR RESEARCH
CENTRE, KARLSRUHE D) 3.21 URENCO S EXPERIENCE WITH REPROCESSED URANIUM,
BY J.A.B. GRESLEY AND 388 J.G. RENOUF (URENCO LTD., MARIOW GB) 3.22 THE
NUSS PORTAL MONITOR FOR ACTIVITY IN BULKY MATERIAL, BY R.C. ROST 392 AND
H. BDCK (NUCLEAR SERVICES AND SUPPLIES (NUSS), VDSENDORF A) 3.23 WASTE
TREATMENT AT RLNGHALS - FROM SOURCE TO FINAL DISPOSAL, BY TORBJORN 395
NLLSSON AND MAGNUS EKENVED (VATTENFALL AB, RINGHALS NPP, VARSBACKA S)
3.24 RADIOACTIVE WASTES FROM STANDARDISED PWR PLANTS, BY I.D. CURRLE,
LM.C. DUTTON AND C. SMEDLEY (NNC LTD, KNUTSFORD GB) 3.25 REPORT ON THE
IRRADIATED FUEL MANAGEMENT IN EASTERN EUROPEAN COUNTRIES AND THE CIS, BY
J. REMADE (COMMISSION OF THE EUROPEAN COMMUNITIES, BRUSSELS B) 3.26
CONFIDENCE-BUILDING IN MODELLING OF RADIONUCLIDE MIGRATION IN FRACTURED
ROCKS - AN INTERNATIONAL EFFORT WITHINASPS HARD ROCK LABORATORY IN
SWEDEN, BY ANDERS STR&M (SWEDISH NUCLEAR FUEL ANDWASTE MANAGEMENT
COMPANY, SKB, STOCKHOLM S) 3.27 THE REGIONAL TOTAL RADIOACTIVE WASTE
MANAGEMENT SYSTEM IN NEXT CENTURY, TOP BY K. K. U (DA-YEH INSTITUTE OF
TECHNOLOGY, CHANGHWA TAIWAN) 30.28 PERFORMANCE ASSESSMENT OF THE
COPPER/STEEL CANISTER, BY PATRLK SELLIN (SKB, STOCKHOLM S) 3.29 COSTS
FOR THE SWEDISH RADIOACTIVE WASTE MANAGEMENT, BY MARIA WIKSTROM TOP
(SKB, STOCKHOLM S) 3.30 GLASS INTERIM STORAGE (E EV T7) WITH COOLING BY
NATURAL CONVECTION, BY E. DE GROMARD (COGEMA, LA HAGUE F) AND P. CANTIN
(SGN, SALNT-EN-QUENTLN -YVELLNES F) 3.31 THE SGN SPENT FUEL DRY VAULT
STORAGE FACILITY, BY C. BONNET AND P. ROUX (SGN, SALNT-QUENTLN-
EN-YVELLNES F) 3.32 GEOCHEMICAL PROBLEMS IN NUCLEAR WASTE DISPOSAL, BY
H. GECKELSAND J.I. KIM (KARLSRUHE NUCLEAR RESEARCH CENTRE, KARLSRUHE D)
3.33 A VERSATILE APPROACH TO MEDIUM TERM SPENT FUEL DRY STORAGE, BY J.
UDDLE (GEO ALSTHOM ENGINEERING SYSTEMS LTD, LEICESTERGB) 3.34
UNDERGROUND WATER CONTAMINATION IN A SPENT FUEL DEPOSIT, BY M. COQUERELL
AND J.P. GLATZ (EUROPEAN COMMISSION, J.R.C., EUROPEAN INSTITUTE FOR
TRANSURANIUM ELEMENTS, KARLSRUHE D) 3.35 DRY VAULT FOR SPENT FUEL
DEPOSITORY BASIC OUTLETS, OPERATING RESULTS AND SAFETY OF THE CASCAD
PLANT, BY PH. BARDELLE AND J-P. MERCLER (CEA C.E. CADARACHE,
ST-PAUL-LEZ-DURANCE F) POSTER SESSION 4 DOWE NEED NEW REACTORS TO
IMPROVE SAFETY AND ECONOMICS? 4.01 EUR, THE EUROPEAN UTILITY
REQUIREMENTS DOCUMENT FOR FUTURE LWR POWER TOP STATIONS, BY D.T. TAYLOR
(NUCLEAR ELECTRIC, KNUTSFORD GB), P. BERBEY (ELECTRLCLT6 DE FRANCE, LYON
F), J ESSMANN (PREUSSENELEKTRA, HANNOVER D), M. DE VALKENEER (TRACTEBEL,
BRUSSELS B), R. REDON (UNESA, MADRID E), L BRUSA (ENEL, ROME I) AND
B.TH. EENDEBAK (NV KEMA, ARNHEM NL) 4.02 EFR PROGRAMME OVERVIEW: A NEW
STEP FORWARD THE FUTURE OF FAST REACTORS, 461 BY G. HUBERT (EDF SEPTEN,
VILLEURBANNE F), P. LAURET (FRAMATOME DIV. NOVATOME, LYON F) AND M.
AUBERT (CEA/DER, SAINT PAUL LEZ DURANCE F) 4.03 SBWR - SIMPLE, PROVEN
AND ECONOMIC TECHNOLOGY FOR THE FUTURE, BY 466 TOP ATAMBLR S. RAO
(GENERAL ELECTRIC COMPANY, SAN JOSE CA, USA) 4.04 SYSTEMS DESIGN OF
DIRECT-CYCLE SUPERCRITICAL-WATER-COOLED REACTORS, 473 BY YOSHIAKL OKA,
SELLCHL KOSHLZUKA, TATJANA JEVREMOVIC AND YASUSHL OKANO (THE UNIVERSITY
OF TOKYO, IBARAKL JAPAN) 4.05 THE CASE FOR VERY SMALL NUCLEAR POWER
PLANTS: CAREM-25, BY SANTIAGO 477 HARRIAGUE (CNEA, CAPITAL FEDERAL
ARGENTINA) AND JUAN PABLO ORDONEZ (INVAP, BARILOCHEARGENTINA) 4.06 FAST
REACTOR GENERIC STUDIES, BY MICHEL AUBERT (EUROPEAN R&D CEA, 481
CADARACHE F) AND JEAN-CLAUDE LEFEVRE (EFR ASSOCIATES FRAMATOME, LYON F)
4.07 EFR PROGRAMME: PLANT DESIGN ACTIVITIES, BY C. H. MITCHELL (NNC
LIMITED, 485 WARRINGTON GB) AND G. HUBERT (SEPTEN, VILLEURBANNE F) 4.08
ALPHA - THE LONG TERM PASSIVE DECAY HEAT REMOVAL AND AEROSOL PROGRAMME,
489 BY C. AUBERT, J. DREIER, 0. FISCHER, S. GUNTAY, M. HUGGENBERGER, S.
LOMPERSKL, G. VARADI, S. VANAR AND G. YADIGAROGLU (PAUL SCHERRER
INSTITUTE, WORENLLNGEN CH) 4.09 STUDIES FOR THE STAGGERED PANS*
CORECATCHER, BY G. FLEG, M. M&SCHKE 494 AND H. WERLE (KARLSRUHE NUCLEAR
RESEARCH CENTRE, KARLSRUHE D) 4.10 THE COMET CORE CATCHER CONCEPT, BY W.
TROMM AND H. ALSMAYER (KARLSRUHE 498 NUCLEAR RESEARCH CENTRE, KARLSRUHE
D) 4.11 EPR SAFETYAPPROACH AND CONSIDERATION OF SEVERE ACCIDENTS, BY
MICHEL 502 E. YVON (NPI, PARIS LA DEFENSE F). JEAN-PIERRE BERGER
(EDF-SEPTEN, VILLEURBANNE F), KARL E. SCHMIDT (PREUSSENELEKTRA, HANNOVER
D) 4.12 ARE DIGITAL INSTRUMENTATION AND CONTROL SYSTEMS SAFE? BY
GEOFFREY IVES 507 (COLENCO POWER CONSULTING LTD., BADEN CH) 4.13
MULTICELL CONTAIN CODE APPLICATIONS FOR AN IMPROVED CONTAINMENT CONCEPT
511 OF FUTURE LIGHT WATER REACTORS, BY G. HENNEGES (KARLSRUHE NUCLEAR
RESEARCH CENTRE, KARLSRUHE D) 4.14 VULCANO: A DEDICATED R&D PROGRAM TO
MASTER CORIUM RECUPERATION FOR 516 FUTURE REACTORS, BY J.C. BOUCHTER AND
G. COGNET (CEA, CE CADARACHE, SALNT-PAUL-LEZ-DURANCE F) 4.15
INVESTIGATIONS ON SUMP COOLING AFTER CORE MELT DOWN, BY J.U. KNEBEL 521
(KARLSRUHE NUCLEAR RESEARCH CENTRE, KARLSRUHE 0) 4.16 ATHENA - A DEVICE
FOR PASSIVE SHUT-DOWN OF FAST REACTORS, BY M. EDEIMANN, 526 W. BAUMANN,
G. KUSSMAUL, J. LEBKOCHER, H. MASSLERAND W. VATH (KARLSRUHE NUCLEAR
RESEARCH CENTRE, KARLSRUHE D) 4.17 ANALYZING THE FLUID DYNAMICS OF
IN-PILE EXPERIMENTS WITH A COMPUTER 530 CODE FOR CORE-DISRUPTIVE
ACCIDENTS, BY DIRK WLLHELM (KARLSRUHE NUCLEAR RESEARCH CENTRE, KARLSRUHE
D) AND GASTON KAYSER (CEA, CE CADARACHE, SAINT-PAUL-LEZ-DURANCE F) 4.18
LOAD CONSEQUENCES OF A REACTOR PRESSURE VESSEL FAILURE AT HIGH PRIMARY
534 SYSTEM PRESSURE, BY GUNTER JACOBS (KARLSRUHE NUCLEAR RESEARCH
CENTRE, KARLSRUHE D) 4.19 MITIGATION OF RECRITLCATLTY ENERGETICS IN A
LMR CORE WITH MINOR ACTINIDES, 538 BY W. MASCHEK AND D. THIEM (KARLSRUHE
NUCLEAR RESEARCH CENTRE, KARLSRUHE D) 4.20 IVA-KA, A THREE-FIELD MODEL
OF PREMIXLNG IN STEAM EXPLOSIONS, BY 542 H. JACOBS, M. LUMMER, B.
STEHLE, K. THURNAY AND L VSTH (KARLSRUHE NUCLEAR RESEARCH CENTRE,
KARLSRUHE D) 4.21 STRUCTURAL RESPONSE TO HYDROGEN COMBUSTION LOADS IN
SEVERE ACCIDENTS, 546 BY W. BRELTUNG AND R. REDLINGER (KARLSRUHE NUCLEAR
RESEARCH CENTRE, KARLSRUHE D) 4.22 ELEMENTS OF INNOVATIVE NUCLEAR
SAFETYTECHNOLOGY BY AGIK, BY B. LELBRECT, 550 M. SAPPOK AND W. STELNWARZ
(SLEMPELKAMP GIESSEREL GMBH & CO., KREFELD D) 4.23 50% (+) EFFICIENT
NUCLEAR REACTORS USING MODERN ENERGY CONVERSION SYSTEMS, 554 BY Z. P.
TLLLLETTE (CONSULTANT TO CEA, CLAMART F) 4.24 PLUTONIUM BURNING AND
MINOR ACTINIDES TRANSMUTATION IN FAST REACTORS: 558 FIRST RESULTS
OBTAINED WITHIN THE FRAME OF THE CAPRA PROGRAMME, BY A. STANCULESCU (EFR
ASSOCIATES (SIEMENS KWU), LYON F), J. C. GAMIER, J. ROUAULT (CEA,
CADARACHE F), E. KIEFHABER (KFK, KARLSRUHE D) AND R. SUNDERLAND (NNC,
RLSLEY GB) 4.25 LOW SOLUBLE BORON CORE EXTENDED-BURNUP CYCLE TO IMPROVE
THE PRESSURISED 565 ALWR SELF-LLMLTLNG CAPABILITIES, BYEDOARDO FIORLNO
(ENEL, ROME I), ENRICO BOTTA AND PRLMO RLSCOSSA (ANSALDO, GENOA I) 4.26
FEASIBILITY STUDY OF MINOR ACTINLDE TRANSMUTATION BWR CORES, BY 569
MOTOO AOYAMA, RYOJI MASUML (ENERGYRESEARCH LABORATORY, HITACHI LTD,
IBARAKL-KEN JAPAN) AND JUNLCHL YAMASHLTA (HITACHI WORKS, HITACHI LTD,
IBARAKL-KEN JAPAN) 4.27 MOX CORE DESIGN OF A DIRECT-CYCLE
SUPERCRITICAL-WATER-COOLED FAST 573 REACTOR, SCFR-D, BY TATJANA
JEVREMOVLC, YOSHIAKI OKA AND SELLCHL KOSHLZUKA (THE UNIVERSITY OF TOKYO,
IBARAKL JAPAN) 4.28 CANFURL AND TANDEM SYSTEMS, BY M. PAVELESCU
(INSTITUTE OF NUCLEAR 577 RESEARCH, PLTESTL ROMANIA) 4.29 CONVERSION
PLUTONIUM AS FUEL FOR WWER-TYPE REACTORS AND SUBCRFTICAL 581 BLANKETS OF
ELECTRO-NUCLEAR FACILITIES, BY A.S. GERASLMOV, T.S. ZARITSKAYA, G.V.
KLSELEV AND A.P. RUDIK (INSTITUTE OF THEORETICAL AND EXPERIMENTAL
PHYSICS, MOSCOW RUSSIA) 4.30 REDUCTION OF LONG-TERM ACTIVATION IN
STRUCTURAL COMPONENTS OF COMMERCIAL 585 TOP REACTORS - A PROMISING TASK
FOR MATERIALS OPTIMIZATION, BY ERIC DAUM AND JOHANNES BERTSCH (KARLSRUHE
NUCLEAR RESEARCH CENTRE, KARLSRUHE D) 4.31 SEGMENTED FUEL RODS CONCEIVED
FOR THE EXPERIMENTATION OF ADVANCED 589 FUEL MATERIALS FOR CURRENT AND
NEW REACTORS, BY M. M. DOMLNGUEZAND L M. MAYO (ENUSA, MADRID E) 4.32
SOME CONCEPTS ON SODIUM-COOLED AND WATER-COOLED REACTORS, BY 593 DLDLER
COSTES (PARIS F)
|
| adam_txt |
ENC '94 INTERNATIONA! NUCLEAR CONGRESS ATOMS FOR ENERGY A DIALOGUE WITH
THE INDUSTRY'S YOUNG GENERATION ON NUCLEAR'S FUTURE EUREXPO, LYON
OCTOBER 2-6, 1994 ORGANIZED BY THE EUROPEAN NUCLEAR SOCIETY, IN
COLLABORATION WITH THE AMERICAN NUCLEAR SOCIETY AND FORATOM CO-SPONSORED
BY: CANADIAN NUCLEAR SOCIETY, CHINESE NUCLEAR SOCIETY, JAPAN ATOMIC
INDUSTRIAL FORUM AND KOREA ATOMIC INDUSTRIAL FORUM VOLUME II POSTER
SESSION PAPERS UB/T1B HANNOVER 89 TABLE OF CONTENTS FOR INVITED PLENARY
SESSION PAPERS SEE VOLUME I TOP = THREE BEST PAPER PER SESSION AWARD
POSTER SESSION 1 THE NEED FOR NUCLEAR ENERGY IN DIFFERENT PARTS OF THE
WORLD 1.01 THE TEN COMMANDMENTS OF UTILITY PLANNING (OR THE CONTINUED
NEED FOR 1 TOP NUCLEAR ENERGY IN THE UNITED STATES, BYMARC S. GERVALS
(NUCLEAR ENERGY INSTITUTE, WASHINGTON, D.C. USA) 1.02 FUNDAMENTAL
REQUIREMENTS FOR ESTABLISHMENT OF NUCLEARPOWER FOR S THE DEVELOPING
COUNTRIES, BY K. K. U (DA-YEN INSTITUTE OF TECHNOLOGY, CHANGHWA TAIWAN)
1.03 THE QUEST FOR ENERGY: NUCLEAR ENERGY OUTLOOK IN TURKEY, BY 9 TOP
KENAN CLNLU (THE UNIVERSITY OF TEXAS IN AUSTIN, TEXAS USA) AND B. NAZLM
BAYRAKTAR (TURKISH ATOMIC ENERGY AUTHORITY, ANKARATURKEY) 1.04 THE
COMPETITIVENESS OF EVOLUTIONARY NUCLEAR PLANTS IN THE UNITED STATES, 13
BY BONN JAMES MACY (NUS, WASHINGTON D.C. USA) 1.05 PRESENT STATUS AND
FUTURE ROLE OF RESEARCH NUCLEAR REACTORS IN 17 INSTITUTE OF NUCLEAR
SCIENCES VINCA, BY MILAN PESLC AND STEFAN CUPAC (INSTITUTE OF NUCLEAR
SCIENCES VINCA, BELGRADE YU) 1.06 COMPARINGTHE ECONOMICS OF NUCLEAR
POWER WITH ALTERNATIVE ELECTRICITY 21 GENERATION OPTIONS IN FINLAND, BY
ANTTL LEHTLIA (TECHNICAL RESEARCH CENTRE OF FINLAND (VTT), ESPOO FIN)
1.07 WOULD HTR BE SUITABLE FOR APPLICATION IN THE NETHERLANDS? BY 25
ALLKL I. VAN HEEK (NETHERLANDS ENERGY FOUNDATION ECN, PETTEN NL) 1.08
CIVIL UTILIZATION OF NUCLEARWEAPON MATERIAL, BY V.M. MUROGOV, M.F.
TROYANOV, 29 V.G. ILUNLN, V.S. KAGRAMANYAN, N.S. RABOTNOV AND V.YA.
RUDNEVA (INSTITUTE OF PHYSICS AND POWER ENGINEERING, OBNINSK RUSSIA)
1.09 CONDITIONS OF RESTARTING THE DEVELOPMENT OF NUCLEARPOWER IN POLAND,
33 BYJACEK MARECKL, KAZLMLERZ T. KOSMOWSKL AND RYSZARD FRYDRYK
(TECHNICAL UNIVERSITY OF GDANSK, GDANSK PL) 1.10 ST. PETERSBURG
(LENINGRAD) NPP'S REGION RADLOECOLOGLCAL STATE ESTIMATION, 37 BY LD.
BLLNOVA (V.G. KHLOPLN RADIUM INSTITUTE, ST. PETERSBURG RUSSIA) 1.11 ST.
PETERSBURG (LENINGRAD) NUCLEAR POWER PLANT: NONRADIOACTIVE IMPACT 40 ON
AQUATIC ENVIRONMENT, BY LM. ZIMLNA (V.G. KHLOPLN RADIUM INSTITUTE, ST.
PETERSBURG RUSSIA) 1.12 PERSPECTIVES OF APPLICATION OF LOW-POWER NUCLEAR
PLANTS IN SAKHA 43 REPUBLIC (YAKUTIA), BY A.YU. ORLOV (THE INSTITUTE OF
PHYSICAL- TECHNICAL PROBLEMS OF THE NORTH OF THE SIBERIAN DIVISION OF
THE RUSSIAN ACADEMY OF SCIENCES, YAKUTSK RUSSIA) 1.13 ENERGY ORIENTED
RESEARCH AT ACCELERATOR LABORATORY IN CROATIA, 47 BY PETARTOMAS (RUDER
BOSKOVLC INSTITUTE, ZAGREB CROATIA) 1.14 SMALL POWER NUCLEAR ENERGY
SOURCES. CONVERSION POTENTIAL. STATUS 51 TOP AND PERSPECTIVES, BY LV.
GUREYEVA, YU. K. PANOV AND E.V. AKHMEDJAYEVA (OKB MECHANICAL
ENGINEERING, NLZNY NOVGOROD RUSSIA) 1.15 AIR POLLUTION OF ATMOSPHERE
FROM DIFFERENT ENERGY SOURCES, BY 59 D. ANTIC, M. SOKCLC-KOSTLC, T.
PAPLC (INSTITUTE OF NUCLEAR SCIENCES "VINCA", NUCLEAR ENGINEERING
LABORATORY, BELGRADE YU) AND B. TELENTA (FEDERAL HYDROMETEOROLOGLCAL
INSTITUTE, BELGRADE YU) 1.16 CURRENT ECONOMIC SITUATION AND ESTIMATED
FUTURE TRENDS OF THE 63 ELECTRICITY GENERATION OPTIONS IN BELGIUM, BY G.
FREDERICK, J.P. GLLLON AND J. DELVOYE (BELGATOM, BRUSSELS B) 1.17 STATUS
OF ELECTRICITY SUPPLY IN REUNIFIED GERMANY, BY DIETERFAUDE 67 (KARLSRUHE
NUCLEAR RESEARCH CENTRE, KARLSRUHE D) POSTER SESSION 2 SAFETY OF
OPERATING NUCLEAR POWER PLANTS 2.01 CONTAINMENT PROTECTION AGAINST
HYDROGEN HAZARDS, BY FERRUCCLO FERRONL 71 (ELECROWATT ENGINEERING
SERVICES LTD., ZURICH CH) PETER COLLINS (SULZER CHEMTECH LTD.,
WLNTERTHUR CH) AND LOTHAR SCHLEL (SULZER THERMTEC LTD., WLNTERTHURCH)
2.02 NEW CONCEPT OF THE ENVIRONMENTAL PROTECTION FROM RADLOAEROSOLS OF
75 CESIUM AND IODINE DURING ACCIDENTS AT NUCLEAR POWER PLANTS, BY
NIKOLAI MLKHEEV, SERGEI KULYUKHLN, ALIA KAMENSKAYA, IGOR RUMER, MIKHAIL
KAZAKEVLCH AND VLTALIL NOVICHENKO (INSTITUTE OF PHYSICAL CHEMISTRY,
RUSSIAN ACADEMY OF SCIENCES, MOSCOW RUSSIA) 2.03 ANALYSIS OF EXTERNAL
PRESSURIZED THERMAL SHOCK, BY ALPO NEUVONEN, 79 PENTTL RAJAMAKL AND OIL!
KYMALALNEN (IVO INTERNATIONAL UD, VANTAA FIN) 2.04 THE SAFE OPERATION
OFLMFBR'S IN SPITE OF THESODIUM FIRE PROBLEMS, BY 83 W. CHERDRON
(KARLSRUHE NUCLEARRESEARCH CENTER, KARLSRUHE D) 2.05 EXPERIMENTS ON THE
CIRCULATIONFLOW RESONANCE IN NATURAL CIRCULATION 87 COOLED BWRS, BY
A.J.C. STEKELENBURG AND T.H.J.J. VAN DER HAGEN (DELFT UNIVERSITY OF
TECHNOLOGY, DELFT NL) 2.06 EFFECTIVENESS OF ECCS DURING LOSS OF COOLANT
ACCIDENT, BY ADREJ PROSEK, 91 BORUT MAVKO AND ANDREJ STRITAR (UNIVERSITY
OF LJUBLJANA, INSTITUTE "JOSEF STEFAN", LJUBLJANA SLO) 2.07 THE SAFETY
OF OPERATING NUCLEAR POWER PLANTS: EVALUATION OF EXTERNAL 95 EVENTS, BY
H.P. BERG, R. G8RTZAND TH. SCHAEFER, BUNDESAMT FUR STRAHLENSCHUTZ,
SALZGLTTER D) 2.08 SURVEY OF FRENCH PWR CORE SEISMIC ANALYSIS, BY
JEAN-CLAUDE LEROUX 99 AND JEAN RIGAUDEAU (FRAMATOME NUCLEAR FUEL, LYON
F) 2.09 STUDY OF CORE RESPONSE IN REACTIVITY ACCIDENTS DUE TO LOCAL
DILUTION 105 OF BORIC ACID CONCENTRATION, BY PERTTL SILTANEN, MARTTI
ANTLLA (IVO INTERNATIONAL LTD, VANTAA FIN) AND RIITTA KYRKI-RAJAMAKL
(VTT ENERGY, ESPOO FIN) 2.10 THE HARMONLSATLON OF METHODS FOR EVALUATING
THE RADIOLOGICAL 112 TOP CONSEQUENCES OF ACCIDENTS AT PWRS, BY LM.C.
DUTTON, C. SMEDLEY (NNC LTD, KNUTSFORD GB) AND W. ESSLER (CEC, BRUSSELS
B) 2.11 RODOS: REAL-TIME ON-LINE DECISION SUPPORT SYSTEM FOR OFF-SITE
116 EMERGENCY MANAGEMENT, BY G. BENZ, M. RAFAT (D.T.I. DR. TRLPPE
INGENLEURGESELLSCHAFT M.B.H, KARLSRUHE D), J. EHRHARDT, D. FAUDE, F.
FISCHER, A. LORENZ, J. PASLER-SAUER, T. SCHLCHTEL, O. SCHCILE AND C.
STELNHAUER (KARLSRUHE NUCLEAR RESEARCH CENTRE, KARLSRUHE D) 2.12
IMPROVED MANAGEMENT OF PRIMARY TO SECONDARY LEAKS AT LOVIISA 120
NUCLEARPOWER PLANT, BY ULLA VUORLO (IVO INTERNATIONAL LTD., VANTAA FIN)
AND ALPO SAVIKOSKL (IMATRAN VOLMA LTD., LOVLLSA FIN) 2.13 SEVERE
ACCIDENT MANAGEMENT GUIDANCE FOR PWRS, BY R.P. PRIOR 124 (WESTLNGHOUSE
ENERGY SYSTEMS EUROPE, BRUSSELS B), R.J. LUTZ, D.K. OHKAWA (WESTLNGHOUSE
ELECTRIC CORPORATION, PITTSBURGH USA) AND J.M. BERMEJO (WESTLNGHOUSE
SISTEMAS ENERGETLCOS ESPANA, MADRID E) 2.14 CATALYTIC RECOMBLNERS FOR
SEVERE ACCIDENT HYDROGEN, BY G.W, KOROLL, 129 W.A. DEWLT, D.W.P. LAU
(AECL RESEARCH, WHLTESHELL LABORATORIES, PLNAWA MANITOBA CAN) AND W.R.C.
GRAHAM (AECL RESEARCH, CHALK RIVER LABORATORIES, CHALK RIVER ONTARIO
CAN) 2.15 AGEING MANAGEMENT THROUGH MAINTENANCE AT TARAPUR, BY SUNIL
GADGLL 132 (TARAPUR ATOMIC POWER STATION, THANE INDIA) 2.16 REMAINING
LIFETIME MANAGEMENT AS A RESPONSE TO THE GROWING DEMANDS 136 ON SAFETY,
ECONOMY AND LIFETIME OF NPPS, BY ESTHER PATOP AND FERNANDO HEVLA
(EMPRESARLOS AGRUPADOS, MADRID E) 2.17 SAFETY AND AVAILABILITY, BY D.
BERQUEZ (FRAMATOME, PARIS F) AND 140 M. MAXANT (EDF, PARIS F) 2.18 CRACK
RISK ASSESSMENT COMPUTATION - APPLICATION TO DEFECT DIAGNOSIS 144 AND
PREVENTIVE MAINTENANCE, BY F. MATTEL, J. HELLOTAND A. LEFRANCOIS
(FRAMATOME, PARIS LA DEFENSE F) 2.19 AN INTEGRATED APPROACH TO LIFE
CYCLE MANAGEMENT, BY MAHENDRA VERMAUT 150 (WESTLNGHOUSE ELECTRIC
CORPORATION, BRUSSELS B) AND MARK KAUSHANSKY (WESTLNGHOUSE ELECTRIC
CORPORATION, PITTSBURGH USA) 2.20 MAINTENANCE COST SAVINGS -SNUBBER
ELIMINATION WITH LIMIT STOPS, BY 156 ROBERT L CLOUD (ROBERT L CLOUD AND
ASSOCIATES, INC., BERKELEY USA), PHILIPPE MONETTE AND ROBERT BALTUS
(WESTLNGHOUSE ELECTRIC CORPORATION, BRUSSELS B) 2.21 EXTENDED LIFETIME
FOR THE REACTOR VESSEL USING LOW LEAKAGE LOADING 162 PATTERN, BY FREDRLK
JOHANSSON (VATTENFALL FUEL, VALLLNGBY S) 2.22 EXTRAPOLATION METHOD FOR
INCORE-EXCORE NUCLEAR INSTRUMENTATION CALIBRATION 165 AT REACTOR
STARTUP, BY MASASHI TAKENO (JAPAN ATOMIC POWERCOMPANY, TSURUGA CITY,
JAPAN), YOICHLRO SHLMASU AND HAJIME YASUL (MITSUBISHI ATOMIC POWER
INDUSTRIES INC., TOKYO JAPAN) 2.23 BACKFITTING A DIGITAL CLASS IE
SYSTEM, BY STEFAN BORLLN AND 169 ANDERS BACK (ABB ATOM, VASTERAS S) 2.24
BENEFITS WITH ABB'S INTEGRATED REACTOR AND TURBINE CONTROLLER CONCEPT,
173 BY EINAR ZETTERGREN, MARTEN AKESSON AND ANDERS RLNGDAHL (ABB ATOM,
VASTERAS S) 2.25 FLOS *A NEW MONITORING SYSTEM FOR LEAK DETECTION AND
LOCATION, BY 177 TOP V. STRELCHER AND P. JAX (SIEMENS AG, ERLANGEN D)
2.26 AN INTEGRATED DIGITAL CONTROL SYSTEM FOR NEW PWRS IN KOREA, BY 181
LL-NAM CHOE (KOREA POWER ENGINEERING CO. INC., SEOUL KOREA) 2.27 IN-SITU
RESPONSE TIME TESTING OF TEMPERATURE AND PRESSURE SENSORS IN 185 NUCLEAR
POWER PLANTS, BY H.M. HASHEMIAN (ANALYSISAND MEASUREMENT SERVICES
CORPORATION, KNOXVLLLE USA) 2.28 NEW METHODS FOR ON-LINE TESTING OF
CALIBRATION OF TEMPERATURE AND 189 PRESSURE SENSORS IN NUCLEARPOWER
PLANTS, BY H.M. HASHEMIAN (ANALYSIS AND MEASUREMENT SERVICES
CORPORATION, KNOXVLLLE USA) 2.29 REACTOR VESSEL HEAD ADAPTER INSPECTION
AND REPAIR, BY A. THOMAS 193 (FRAMATOME, LYON F) 2.30 UTS UNIVERSAL
TESTING SWORD, BY PER SJ&BERG (ABB TEKNLSKA 197 RFLNTGENCENTRALEN AB
(TRC), TFIBY S) 2.31 UNISESAM: NEXT GENERATION RPV ID-INSPECTION TOOL,
BY LARS DRUGGE 201 (ABB TEKNLSKA RDNTGENCENTRALEN AB (TRC), TABY S) 2.32
PWR BOTTOM NOZZLE INSPECTION, BY MARLKAWESTMAN (ABB TEKNLSKA 205
RFLNTGENCENTRALEN AB (TRC), TABY S) 2.33 LEADING EDGE SAFETY SHUTDOWN
SYSTEM, BY ALLSTALR SMITH AND KEITH 208 MCMINN (NNC LTD, KNUTSFORD GB)
2.34 CONTROL ROD DRIVE MONITORING SYSTEM, BY JIRI USKA, KAREL DVORAK 211
AND FRANTLSEK DALLK (SKODA, PLZEN CZ) 2.35 INTRODUCTION OF GADOLINIUM AS
A PWR INTEGRAL BURNABLE POISON IN THE 214 SPANISH NUCLEAR INDUSTRY, BY
F. MERINO AND M.A. MONTES (ENUSA, MADRID E) 2.36 PWR FUEL IN JAPAN -
PROGRESS AND FUTURE TRENDS, BY MLTSUHLRO YOKOTA 218 (KANSAL ELECTRIC
POWER CO., OSAKA JAPAN), YOSHLAKI KONDO (NUCLEAR DEVELOPMENT COMPANY
JAPAN) AND SADAAKI ABETA (MITSUBISHI HEAVY INDUSTRIES, YOKOHAMA JAPAN)
2.37 EXPERIMENTALWER SAFETY STUDIES IN FINLAND, BY PEKKA RAUSSL, RELJO
222 MUNTHER, HELKKI KAIL! (LAPPEENRANTA UNIVERSITY OF TECHNOLOGY,
LAPPEENRANTA FIN), JYRKI KOUHLA AND MARKKU PUUSTLNEN (VTT ENERGY,
LAPPEENRANTA FIN) 2.38 RADIOACTIVE CONTAMINATION OF THE ENVIRONMENT IN
THE AREAS OF NPPS 226 WITH REACTORS OF THEWER AND RBMK TYPE, BY I.I.
KRYSHEV (SCIENTIFIC PRODUCTION ASSOCIATIONTYPHOON", OBNINSK RUSSIA) 2.39
SAFETY IMPROVEMENT OFWER - THE ENAC CONTRIBUTION, BY D. TAYLOR 230
(ENAC, BRUSSELS B) AND E.L INGHAM (NNC LTD, KNUTSFORD GB) 2.40 L&C
REPLACEMENTS FORWER TYPE 440/V213 NPPS, BY A.F. PARSONS 234 AND D.P.D.
WHLTWORTH (NNC LTD, KNUTSFORD GB) 2.41 SYSTEM FOR EARLY EMERGENCY
PROGNOSIS AND RESPONSE CENTERS, BY 237 YU.L TSOGLLN, V.I. BORLSENKO,
I.A. KLLMENKO, V.S. LYUBARSKY AND N.M. SLDORUCK (INSTITUTE FOR NUCLEAR
RESEARCH, NATIONAL ACADEMY OF SCIENCE OF UKRAINE, KIEV UKRAINE) 2.42 THE
DUKOVANY NPP * THE PAST, THE PRESENTAND PROSPECTS OF FURTHER 241
OPERATION, BY ZDENEK LLNHART AND MIROSLAV TRNKA, (NPP DUKOVANY, DUKOVANY
CZ) 2.43 EXPERIMENTS ON THE DETERMINATION OFWERZ-M-10 RESEARCH REACTOR
POWER 245 BY N-16 ACTIVITY MONITORING, BY I. BENKOVLCS (KFKI MTA,
BUDAPEST H), K. ERDELYL, I. ALMASL AND I. SZENDRD (MLCROVACUUM LTD.,
BUDAPEST H) 2.44 THE MAIN PRINCIPLES OF TECHNICAL SECURITY SYSTEMS
DEVELOPMENT FOR 247 RUSSIAN POWER PLANTS PHYSICAL PROTECTION, BY
ALEXANDER V. IZMALLOV (SPECIAL SCIENTIFIC & PRODUCTION STATE ENTERPRISE
"ELERON", MOSCOW RUSSIA) 2.45 RINGHAIS NPP, UNIT 1 DESIGN BASES RENEWAL
PROGRAMME, BY MARIA HENRIKSSON, 251 JAN LADEBORN AND CARINA KARLSSON
(VATTENFALL AB, RLNGHALS NPP, VSROBACKA S) 2.46 INNOVATIVE SAFETY
FEATURES OF THE N4 PLANT DESIGN, BY D. LANGE 254 TOP (FRAMATOME, PARIS
F) AND B. VLDAL (EDF SEPTEN, VLLLEURBANNE F) 2.47 EMDISY - TOOL TO
SUPPORT OPERATOR DURING EMERGENCY, BY IGOR SALAMUN, 258 BORUT MAVKO AND
ANDREJ STRLTAR (UNIVERSITY OF LJUBLJANA, INSTITUTE "JOSEF STEFAN",
LJUBLJANA SLO) 2.48 DIMOS: THE WAY TO REALIZE HARMONY BETWEEN THE
OPERATOR AND THE NUCLEAR 262 PROCESS, BY GEERT UYTTERHOEVEN, MICHEL DE
VLAMINCK AND BERNARD GILLLOT (BELGATOM, BRUSSELS B) 2.49 RADIATION
PROTECTION EXPERIENCE IN NONSTANDARD OPERATION OF FIRST 267 YUGOSLAV
REACTOR RB, BY M.M NINKOVIC AND J.J. RALCEVLC (INSTITUTE OF NUCLEAR
SCIENCES VINCA, BELGRADE YU) 2.50 ROOT CAUSE ANALYSIS, BY OLLL NEVANDER
(IVO INTERNATIONAL LTD, VANTAA FIN) 271 AND JARL SNELLMAN (IVO LOVLLSA
NPP, LOVLISA FIN) 2.51 A PLANT INFORMATION SYSTEM IN LINE WITH L&C
UPGRADE, BY PASCAL ANCLON 275 (WESTLNGHOUSE ELECTRIC CORPORATION,
BRUSSELS B) 2.52 FEEDBACK FROM EXPERIENCE GAINED WITH STEAM GENERATORS
REPLACEMENT 279 AT DOEL 3 NPP (BELGIUM), BY MARC LEPLECE AND FRANCLNE
VERMLNNEN (BELGATOM, BRUSSELS B) 2.53 TRAINING AND QUALITY, BY NATHALIE
IDRLSSL (FRAMATOME, PARIS LA DEFENCE F) 286 2.54 TECHNICAL AND
ECONOMICAL BENEFITS FROM RISK- AND PREDICTION ANALYSES AT 290 AGEING
MANAGEMENT PROGRAM, BY S6REN STRLDSBERG (ABB ATOM, VASTERAS S) POSTER
SESSION 3 BACK-END OF THE FUEL CYCLE: RECYCLING AND DIRECT STORAGE OF
FUEL ELEMENTS 3.01 DESIGNAND ERECTION OF THE PILOT PLANT FOR SPENT FUEL
CONDITIONING, 294 BY M. WINTER, I. HLLDEBRANDT AND J. BALER (NOELL GMBH,
WURZBURG D) 3.02 THE BEHAVIOUR OF NP IN A NITRIC ACID U-PU PARTITION
PROCESS, 298 BY YASUO HLROSE (HITACHI WORKS, HITACHI JAPAN), YOLCHL
TAKASHLMA AND YASUHLSA IKEDA (INSTITUTE OF RESEARCH AND INNOVATION,TOKYO
JAPAN) 3.03 SPENT FUELS CONDITIONING AND IRRADIATED NUCLEAR FUEL
ELEMENTS 303 EXAMINATION: THE STAR FACILITYAND ITS PROCESSES, BY F.
BOUSSARD, R. HULLLERY (CEA, CADARACHE F), J.L AVERSENG AND J.P.
SERPANTLE (FRAMATOME/NOVATOME, LYON F) 3.04 TREATMENT OF SPENT
GRANULATED NATURAL SORBENTS FOR FURTHER SAFE 307 HANDLING AND STORAGE,
BY S.YU. SAYENKO, R.V. TARASOV AND V.P. KANTSEDAL (NATIONAL SCIENCE
CENTRE KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY (KIPT), KHARKOV
UKRAINE) 3.05 EFFECTIVE IMPLEMENTATION AND ASSESSMENT OF THE SAFETY AT
THE UP 3 311 REPROCESSING PLANT, BY G. DUBOIS (COGEMA, VELTZY F) 3.06
TREATMENT OF RADIOACTIVE EFFLUENTS USING ENHANCED ULTRAFILTRATION, BY
316 R. LIBERGE, C. REDONNET (SGN, SALNT-QUENTLN-EN-YVELLNES F), P. HURON
AND J.-M. FERNANDEZ (COGEMA, LA HAGUE F) 3.07 ELECTROGENERATED AG II FOR
RECOVERY OF PU02 FROM WASTE, BY M.-H. MOULLNEY, 321 F.-J. PONCELET, P.
MIQUEL (SGN, SALNT-QUENTLN-EN-YVELLNES F), V. DECOBERT (COGEMA, VELIZY
F) AND M. LECOMTE (CEA, SACLAY F) 3.08 FIBER REINFORCED CONCRETE
CONTAINERS, BY A. VERDIER (SOGEFLBRE, SAINT- 326 QUENTLN-EN-YVELLNES F)
AND J.-C. DELRLEU (SGN, SALNT-QUENTLN-EN-YVELLNES F) 3.09 ALPHA WASTE
INCINERATION, BY J.-PH. DUREC, E. DE SAULLEU (SGN, SAINT- 332
QUENTLN-EN-YVELLNES F) AND J. LANNAUD (CEA, VALDUC F) 3.10 OPTIMIZATION
OF WASTE MANAGEMENT AT THE LA HAGUE UP3 PLANT, BY 337 C. BERNARD (SGN,
SALNT-QUENTLN-EN-YVELLNES F) AND P. LEDERMANN (COGEMA, LA HAGUE F) 3.11
APPLICATION OF INDUCTIVELY COUPLED PLASMA/EMISSION SPECTROMETRY TO 341
LABORATORY ANALYSES, BY J. BESNTER (COGEMA, LA HAGUE F), L BROMET AND J.
HUNI (SGN, SAINT-QUENTLN-EN-YVELINES F) 3.12 ADVANCED REPROSESSING OF
SPENT NUCLEAR FUELS, BY J.P. GLATZ, Y. MOR ITA, 345 C. SONG AND L KOCH
(EUROPEAN COMMISSION, J.R.C., EUROPEAN INSTITUTE FOR TRANSURANIUM
ELEMENTS, KARLSRUHE D) 3.13 IMPROVEMENTS IN FUEL MANUFACTURING
EQUIPMENTAND PROCEDURES FOR INDUSTRIAL 349 PRODUCTION OF REPROCESSED
URANIUM FUEL RELOADS, BY JEAN HENCKES, CHRISTIAN DELEVALLEE AND PHILIPPE
DEWEZ (FBFC, ROMANS F) 3.14 INCREASE OF THE QUANTITY OF PLUTONIUM
RECYCLED WITHIN FRENCH 900 MWE 353 PLANTS - MOX 95 FEASIBILITY STUDIES,
BY ALEXIS MARLNCIC, FRANGOIS-YVES GUENA (FRAMATOME, PARIS LA DEFENSE F)
AND XAVIER THLBAULT (EDF/SEPTEN, VILLEURBANNE F) 3.15 A COHERENT
STRATEGY FOR PLUTONIUM AND ACTINLDE RECYCLING, BY J. TOMMASI, 358 J.C.
GARNLER (CEA - C.E. CADARACHE, ST-PAUI-LEZ-DURANCE F) AND D. VERRLER
(FRAMATOME/NOVATOME, LYON F) 3.16 PWR'S POTENTIALITIES FOR PLUTONIUM
RECYCLING AND MINOR ACTINIDES BURNING, 362 BY M. DELPECH, R. GLRIEUD
(CEA DER/SPRC - C.E. CADARACHE, ST-PAUWEZ- DURANCE F) AND G. MANENT (CEA
DER/SIS - C.E. CADARACHE, ST-PAUMEZ- DURANCE F) 3.17 MOX FUEL IN PWR'S:
STATUS AND OUTLOOK, BY MICHEL DELOR, FRANCK OBADIA 367 TOP (FRAMATOME,
LYON F), JEAN-LUC GUILLET AND CLAUDE GOLLNELLL (COGEMA, VETIZY F) 3.18
RECYCLING OF ACTINIDESAND FISSION PRODUCTS, THE DUTCH RAS RESEARCH 375
PROGRAMME, BY K. ABRAHAMS, E.H.P. CORDFUNKE, W.M.P. FRANKEN, H.
GRUPPELAAR, J.LKIOOSTERMAN, R.J.M. KONLNGS AND A.M. VERSTEEGH
(NETHERLANDS ENERGY RESEARCH FOUNDATION ECN, PETTEN NL) 3.19 SVEA-96
DESIGNS FOR BWR MOX ASSEMBLIES, BY LARS PAULSSON (ABB ATOM, 379 VASTERAS
S) AND JOSEPH AFONSO (ELEKTROWATT ENGINEERING SERVICES LTD, ZURICH CH)
3.20 SENSITIVITY OF THE SUPPORT RATIO IN FAST REACTOR INCINERATION
CALCULATIONS, 384 BY H.W. WIESE AND B. KRLEG (KARLSRUHE NUCLEAR RESEARCH
CENTRE, KARLSRUHE D) 3.21 URENCO'S EXPERIENCE WITH REPROCESSED URANIUM,
BY J.A.B. GRESLEY AND 388 J.G. RENOUF (URENCO LTD., MARIOW GB) 3.22 THE
NUSS PORTAL MONITOR FOR ACTIVITY IN BULKY MATERIAL, BY R.C. ROST 392 AND
H. BDCK (NUCLEAR SERVICES AND SUPPLIES (NUSS), VDSENDORF A) 3.23 WASTE
TREATMENT AT RLNGHALS - FROM SOURCE TO FINAL DISPOSAL, BY TORBJORN 395
NLLSSON AND MAGNUS EKENVED (VATTENFALL AB, RINGHALS NPP, VARSBACKA S)
3.24 RADIOACTIVE WASTES FROM STANDARDISED PWR PLANTS, BY I.D. CURRLE,
LM.C. DUTTON AND C. SMEDLEY (NNC LTD, KNUTSFORD GB) 3.25 REPORT ON THE
IRRADIATED FUEL MANAGEMENT IN EASTERN EUROPEAN COUNTRIES AND THE CIS, BY
J. REMADE (COMMISSION OF THE EUROPEAN COMMUNITIES, BRUSSELS B) 3.26
CONFIDENCE-BUILDING IN MODELLING OF RADIONUCLIDE MIGRATION IN FRACTURED
ROCKS - AN INTERNATIONAL EFFORT WITHINASPS HARD ROCK LABORATORY IN
SWEDEN, BY ANDERS STR&M (SWEDISH NUCLEAR FUEL ANDWASTE MANAGEMENT
COMPANY, SKB, STOCKHOLM S) 3.27 THE REGIONAL TOTAL RADIOACTIVE WASTE
MANAGEMENT SYSTEM IN NEXT CENTURY, TOP BY K. K. U (DA-YEH INSTITUTE OF
TECHNOLOGY, CHANGHWA TAIWAN) 30.28 PERFORMANCE ASSESSMENT OF THE
COPPER/STEEL CANISTER, BY PATRLK SELLIN (SKB, STOCKHOLM S) 3.29 COSTS
FOR THE SWEDISH RADIOACTIVE WASTE MANAGEMENT, BY MARIA WIKSTROM TOP
(SKB, STOCKHOLM S) 3.30 GLASS INTERIM STORAGE (E EV T7) WITH COOLING BY
NATURAL CONVECTION, BY E. DE GROMARD (COGEMA, LA HAGUE F) AND P. CANTIN
(SGN, SALNT-EN-QUENTLN -YVELLNES F) 3.31 THE SGN SPENT FUEL DRY VAULT
STORAGE FACILITY, BY C. BONNET AND P. ROUX (SGN, SALNT-QUENTLN-
EN-YVELLNES F) 3.32 GEOCHEMICAL PROBLEMS IN NUCLEAR WASTE DISPOSAL, BY
H. GECKELSAND J.I. KIM (KARLSRUHE NUCLEAR RESEARCH CENTRE, KARLSRUHE D)
3.33 A VERSATILE APPROACH TO MEDIUM TERM SPENT FUEL DRY STORAGE, BY J.
UDDLE (GEO ALSTHOM ENGINEERING SYSTEMS LTD, LEICESTERGB) 3.34
UNDERGROUND WATER CONTAMINATION IN A SPENT FUEL DEPOSIT, BY M. COQUERELL
AND J.P. GLATZ (EUROPEAN COMMISSION, J.R.C., EUROPEAN INSTITUTE FOR
TRANSURANIUM ELEMENTS, KARLSRUHE D) 3.35 DRY VAULT FOR SPENT FUEL
DEPOSITORY BASIC OUTLETS, OPERATING RESULTS AND SAFETY OF THE CASCAD
PLANT, BY PH. BARDELLE AND J-P. MERCLER (CEA C.E. CADARACHE,
ST-PAUL-LEZ-DURANCE F) POSTER SESSION 4 DOWE NEED NEW REACTORS TO
IMPROVE SAFETY AND ECONOMICS? 4.01 EUR, THE EUROPEAN UTILITY
REQUIREMENTS DOCUMENT FOR FUTURE LWR POWER TOP STATIONS, BY D.T. TAYLOR
(NUCLEAR ELECTRIC, KNUTSFORD GB), P. BERBEY (ELECTRLCLT6 DE FRANCE, LYON
F), J ESSMANN (PREUSSENELEKTRA, HANNOVER D), M. DE VALKENEER (TRACTEBEL,
BRUSSELS B), R. REDON (UNESA, MADRID E), L BRUSA (ENEL, ROME I) AND
B.TH. EENDEBAK (NV KEMA, ARNHEM NL) 4.02 EFR PROGRAMME OVERVIEW: A NEW
STEP FORWARD THE FUTURE OF FAST REACTORS, 461 BY G. HUBERT (EDF SEPTEN,
VILLEURBANNE F), P. LAURET (FRAMATOME DIV. NOVATOME, LYON F) AND M.
AUBERT (CEA/DER, SAINT PAUL LEZ DURANCE F) 4.03 SBWR - SIMPLE, PROVEN
AND ECONOMIC TECHNOLOGY FOR THE FUTURE, BY 466 TOP ATAMBLR S. RAO
(GENERAL ELECTRIC COMPANY, SAN JOSE CA, USA) 4.04 SYSTEMS DESIGN OF
DIRECT-CYCLE SUPERCRITICAL-WATER-COOLED REACTORS, 473 BY YOSHIAKL OKA,
SELLCHL KOSHLZUKA, TATJANA JEVREMOVIC AND YASUSHL OKANO (THE UNIVERSITY
OF TOKYO, IBARAKL JAPAN) 4.05 THE CASE FOR VERY SMALL NUCLEAR POWER
PLANTS: CAREM-25, BY SANTIAGO 477 HARRIAGUE (CNEA, CAPITAL FEDERAL
ARGENTINA) AND JUAN PABLO ORDONEZ (INVAP, BARILOCHEARGENTINA) 4.06 FAST
REACTOR GENERIC STUDIES, BY MICHEL AUBERT (EUROPEAN R&D CEA, 481
CADARACHE F) AND JEAN-CLAUDE LEFEVRE (EFR ASSOCIATES FRAMATOME, LYON F)
4.07 EFR PROGRAMME: PLANT DESIGN ACTIVITIES, BY C. H. MITCHELL (NNC
LIMITED, 485 WARRINGTON GB) AND G. HUBERT (SEPTEN, VILLEURBANNE F) 4.08
ALPHA - THE LONG TERM PASSIVE DECAY HEAT REMOVAL AND AEROSOL PROGRAMME,
489 BY C. AUBERT, J. DREIER, 0. FISCHER, S. GUNTAY, M. HUGGENBERGER, S.
LOMPERSKL, G. VARADI, S. VANAR AND G. YADIGAROGLU (PAUL SCHERRER
INSTITUTE, WORENLLNGEN CH) 4.09 STUDIES FOR THE "STAGGERED PANS*
CORECATCHER, BY G. FLEG, M. M&SCHKE 494 AND H. WERLE (KARLSRUHE NUCLEAR
RESEARCH CENTRE, KARLSRUHE D) 4.10 THE COMET CORE CATCHER CONCEPT, BY W.
TROMM AND H. ALSMAYER (KARLSRUHE 498 NUCLEAR RESEARCH CENTRE, KARLSRUHE
D) 4.11 EPR SAFETYAPPROACH AND CONSIDERATION OF SEVERE ACCIDENTS, BY
MICHEL 502 E. YVON (NPI, PARIS LA DEFENSE F). JEAN-PIERRE BERGER
(EDF-SEPTEN, VILLEURBANNE F), KARL E. SCHMIDT (PREUSSENELEKTRA, HANNOVER
D) 4.12 ARE DIGITAL INSTRUMENTATION AND CONTROL SYSTEMS SAFE? BY
GEOFFREY IVES 507 (COLENCO POWER CONSULTING LTD., BADEN CH) 4.13
MULTICELL CONTAIN CODE APPLICATIONS FOR AN IMPROVED CONTAINMENT CONCEPT
511 OF FUTURE LIGHT WATER REACTORS, BY G. HENNEGES (KARLSRUHE NUCLEAR
RESEARCH CENTRE, KARLSRUHE D) 4.14 VULCANO: A DEDICATED R&D PROGRAM TO
MASTER CORIUM RECUPERATION FOR 516 FUTURE REACTORS, BY J.C. BOUCHTER AND
G. COGNET (CEA, CE CADARACHE, SALNT-PAUL-LEZ-DURANCE F) 4.15
INVESTIGATIONS ON SUMP COOLING AFTER CORE MELT DOWN, BY J.U. KNEBEL 521
(KARLSRUHE NUCLEAR RESEARCH CENTRE, KARLSRUHE 0) 4.16 ATHENA - A DEVICE
FOR PASSIVE SHUT-DOWN OF FAST REACTORS, BY M. EDEIMANN, 526 W. BAUMANN,
G. KUSSMAUL, J. LEBKOCHER, H. MASSLERAND W. VATH (KARLSRUHE NUCLEAR
RESEARCH CENTRE, KARLSRUHE D) 4.17 ANALYZING THE FLUID DYNAMICS OF
IN-PILE EXPERIMENTS WITH A COMPUTER 530 CODE FOR CORE-DISRUPTIVE
ACCIDENTS, BY DIRK WLLHELM (KARLSRUHE NUCLEAR RESEARCH CENTRE, KARLSRUHE
D) AND GASTON KAYSER (CEA, CE CADARACHE, SAINT-PAUL-LEZ-DURANCE F) 4.18
LOAD CONSEQUENCES OF A REACTOR PRESSURE VESSEL FAILURE AT HIGH PRIMARY
534 SYSTEM PRESSURE, BY GUNTER JACOBS (KARLSRUHE NUCLEAR RESEARCH
CENTRE, KARLSRUHE D) 4.19 MITIGATION OF RECRITLCATLTY ENERGETICS IN A
LMR CORE WITH MINOR ACTINIDES, 538 BY W. MASCHEK AND D. THIEM (KARLSRUHE
NUCLEAR RESEARCH CENTRE, KARLSRUHE D) 4.20 IVA-KA, A THREE-FIELD MODEL
OF PREMIXLNG IN STEAM EXPLOSIONS, BY 542 H. JACOBS, M. LUMMER, B.
STEHLE, K. THURNAY AND L VSTH (KARLSRUHE NUCLEAR RESEARCH CENTRE,
KARLSRUHE D) 4.21 STRUCTURAL RESPONSE TO HYDROGEN COMBUSTION LOADS IN
SEVERE ACCIDENTS, 546 BY W. BRELTUNG AND R. REDLINGER (KARLSRUHE NUCLEAR
RESEARCH CENTRE, KARLSRUHE D) 4.22 ELEMENTS OF INNOVATIVE NUCLEAR
SAFETYTECHNOLOGY BY AGIK, BY B. LELBRECT, 550 M. SAPPOK AND W. STELNWARZ
(SLEMPELKAMP GIESSEREL GMBH & CO., KREFELD D) 4.23 50% (+) EFFICIENT
NUCLEAR REACTORS USING MODERN ENERGY CONVERSION SYSTEMS, 554 BY Z. P.
TLLLLETTE (CONSULTANT TO CEA, CLAMART F) 4.24 PLUTONIUM BURNING AND
MINOR ACTINIDES TRANSMUTATION IN FAST REACTORS: 558 FIRST RESULTS
OBTAINED WITHIN THE FRAME OF THE CAPRA PROGRAMME, BY A. STANCULESCU (EFR
ASSOCIATES (SIEMENS KWU), LYON F), J. C. GAMIER, J. ROUAULT (CEA,
CADARACHE F), E. KIEFHABER (KFK, KARLSRUHE D) AND R. SUNDERLAND (NNC,
RLSLEY GB) 4.25 LOW SOLUBLE BORON CORE EXTENDED-BURNUP CYCLE TO IMPROVE
THE PRESSURISED 565 ALWR SELF-LLMLTLNG CAPABILITIES, BYEDOARDO FIORLNO
(ENEL, ROME I), ENRICO BOTTA AND PRLMO RLSCOSSA (ANSALDO, GENOA I) 4.26
FEASIBILITY STUDY OF MINOR ACTINLDE TRANSMUTATION BWR CORES, BY 569
MOTOO AOYAMA, RYOJI MASUML (ENERGYRESEARCH LABORATORY, HITACHI LTD,
IBARAKL-KEN JAPAN) AND JUNLCHL YAMASHLTA (HITACHI WORKS, HITACHI LTD,
IBARAKL-KEN JAPAN) 4.27 MOX CORE DESIGN OF A DIRECT-CYCLE
SUPERCRITICAL-WATER-COOLED FAST 573 REACTOR, SCFR-D, BY TATJANA
JEVREMOVLC, YOSHIAKI OKA AND SELLCHL KOSHLZUKA (THE UNIVERSITY OF TOKYO,
IBARAKL JAPAN) 4.28 CANFURL AND TANDEM SYSTEMS, BY M. PAVELESCU
(INSTITUTE OF NUCLEAR 577 RESEARCH, PLTESTL ROMANIA) 4.29 CONVERSION
PLUTONIUM AS FUEL FOR WWER-TYPE REACTORS AND SUBCRFTICAL 581 BLANKETS OF
ELECTRO-NUCLEAR FACILITIES, BY A.S. GERASLMOV, T.S. ZARITSKAYA, G.V.
KLSELEV AND A.P. RUDIK (INSTITUTE OF THEORETICAL AND EXPERIMENTAL
PHYSICS, MOSCOW RUSSIA) 4.30 REDUCTION OF LONG-TERM ACTIVATION IN
STRUCTURAL COMPONENTS OF COMMERCIAL 585 TOP REACTORS - A PROMISING TASK
FOR MATERIALS OPTIMIZATION, BY ERIC DAUM AND JOHANNES BERTSCH (KARLSRUHE
NUCLEAR RESEARCH CENTRE, KARLSRUHE D) 4.31 SEGMENTED FUEL RODS CONCEIVED
FOR THE EXPERIMENTATION OF ADVANCED 589 FUEL MATERIALS FOR CURRENT AND
NEW REACTORS, BY M. M. DOMLNGUEZAND L M. MAYO (ENUSA, MADRID E) 4.32
SOME CONCEPTS ON SODIUM-COOLED AND WATER-COOLED REACTORS, BY 593 DLDLER
COSTES (PARIS F) |
| any_adam_object | 1 |
| any_adam_object_boolean | 1 |
| author_corporate | ENC Lyon |
| author_corporate_role | aut |
| author_facet | ENC Lyon |
| author_sort | ENC Lyon |
| building | Verbundindex |
| bvnumber | BV022074818 |
| ctrlnum | (OCoLC)37573264 (DE-599)BVBBV022074818 |
| format | Conference Proceeding Book |
| fullrecord | <?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>01177nam a2200277zcc4500</leader><controlfield tag="001">BV022074818</controlfield><controlfield tag="003">DE-604</controlfield><controlfield tag="005">20060314000000.0</controlfield><controlfield tag="007">t</controlfield><controlfield tag="008">960614s1994 d||| |||| 10||| eng d</controlfield><datafield tag="020" ind1=" " ind2=" "><subfield code="a">3952069108</subfield><subfield code="9">3-9520691-0-8</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(OCoLC)37573264</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-599)BVBBV022074818</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">DE-604</subfield><subfield code="b">ger</subfield></datafield><datafield tag="041" ind1="0" ind2=" "><subfield code="a">eng</subfield></datafield><datafield tag="049" ind1=" " ind2=" "><subfield code="a">DE-706</subfield></datafield><datafield tag="111" ind1="2" ind2=" "><subfield code="a">ENC</subfield><subfield code="d">1994</subfield><subfield code="c">Lyon</subfield><subfield code="j">Verfasser</subfield><subfield code="0">(DE-588)2160079-X</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">ENC '94</subfield><subfield code="b">International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994</subfield><subfield code="n">1994,2</subfield><subfield code="p">Poster session papers</subfield><subfield code="c">organized by the European Nuclear Society ...</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="a">Bern</subfield><subfield code="b">ENS</subfield><subfield code="c">1994</subfield></datafield><datafield tag="300" ind1=" " ind2=" "><subfield code="a">596 S.</subfield><subfield code="b">graph. Darst.</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="b">n</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="b">nc</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="773" ind1="0" ind2="8"><subfield code="w">(DE-604)BV021856588</subfield><subfield code="g">1994,2</subfield></datafield><datafield tag="856" ind1="4" ind2="2"><subfield code="m">GBV Datenaustausch</subfield><subfield code="q">application/pdf</subfield><subfield code="u">http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=015289616&sequence=000001&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA</subfield><subfield code="3">Inhaltsverzeichnis</subfield></datafield><datafield tag="999" ind1=" " ind2=" "><subfield code="a">oai:aleph.bib-bvb.de:BVB01-015289616</subfield></datafield></record></collection> |
| id | DE-604.BV022074818 |
| illustrated | Illustrated |
| index_date | 2024-07-02T16:14:02Z |
| indexdate | 2024-07-09T20:50:14Z |
| institution | BVB |
| institution_GND | (DE-588)2160079-X |
| isbn | 3952069108 |
| language | English |
| oai_aleph_id | oai:aleph.bib-bvb.de:BVB01-015289616 |
| oclc_num | 37573264 |
| open_access_boolean | |
| owner | DE-706 |
| owner_facet | DE-706 |
| physical | 596 S. graph. Darst. |
| publishDate | 1994 |
| publishDateSearch | 1994 |
| publishDateSort | 1994 |
| publisher | ENS |
| record_format | marc |
| spelling | ENC 1994 Lyon Verfasser (DE-588)2160079-X aut ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 1994,2 Poster session papers organized by the European Nuclear Society ... Bern ENS 1994 596 S. graph. Darst. txt rdacontent n rdamedia nc rdacarrier (DE-604)BV021856588 1994,2 GBV Datenaustausch application/pdf http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=015289616&sequence=000001&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA Inhaltsverzeichnis |
| spellingShingle | ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 |
| title | ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 |
| title_auth | ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 |
| title_exact_search | ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 |
| title_exact_search_txtP | ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 |
| title_full | ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 1994,2 Poster session papers organized by the European Nuclear Society ... |
| title_fullStr | ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 1994,2 Poster session papers organized by the European Nuclear Society ... |
| title_full_unstemmed | ENC '94 International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 1994,2 Poster session papers organized by the European Nuclear Society ... |
| title_short | ENC '94 |
| title_sort | enc 94 international nuclear congress atoms for energy a dialogue with the industry s young generation on nuclear s future eurexpo lyon october 2 6 1994 poster session papers |
| title_sub | International Nuclear Congress Atoms for Energy ; a dialogue with the industry's young generation on nuclear's future ; Eurexpo, Lyon, October 2 - 6, 1994 |
| url | http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=015289616&sequence=000001&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA |
| volume_link | (DE-604)BV021856588 |
| work_keys_str_mv | AT enclyon enc94internationalnuclearcongressatomsforenergyadialoguewiththeindustrysyounggenerationonnuclearsfutureeurexpolyonoctober26199419942 |