ENC '94

Internationa! Nuclear CongressAtoms 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, by Marc S. Gervals (NuclearEnergy Institute, Washington, D.C. USA)

1.02 Fundamental requirements for establishment of nuclear power for Sthe 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, Ankara TURKEY)

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 Comparing the 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 nuclear weapon material, by V.M. Murogov, M.F. Troyanov, 29

V.G. Ilunln, V.S. Kagramanyan, N.S. Rabotnov and V.Ya. Rudneva (Instituteof Physics and Power Engineering, Obninsk RUSSIA)

1.09 Conditions of restarting the development of nuclear power In Poland, 33

by Jacek 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 40on 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 Petar Tomas (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 Dieter Faude 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 (SulzerThermtec Ltd., Wlnterthur CH)

2.02 New concept of the environmental protection from radloaerosols of 75

cesium and Iodine during accidents at nuclear power plants, byNikolai Mlkheev, Sergei Kulyukhln, Alia Kamenskaya, Igor Rumer,

Mikhail Kazakevlch and Vltalil Novichenko (Institute of PhysicalChemistry, 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 of LMFBR's In spite of the sodium fire problems, by 83

W. Cherdron (Karlsruhe Nuclear Research Center, Karlsruhe D)

2.05 Experiments on the circulation flow 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. G8rtz and 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

nuclear power 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. Hellot and 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 Power Company,Tsuruga City, JAPAN), Yoichlro Shlmasu and Hajime Yasul (MitsubishiAtomic 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 177TOP 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 (Analysis and Measurement

Services Corporation, Knoxvllle USA)

2.28 New methods for On-Line testing of calibration of temperature and 189

pressure sensors In nuclear power plants, by H.M. Hashemian (Analysisand 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 Marlka Westman (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 (NuclearDevelopment Company JAPAN) and Sadaaki Abeta (Mitsubishi HeavyIndustries, Yokohama JAPAN)

2.37 Experimental WER 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 226with reactors of the WER and RBMK type, by I.I. Kryshev (ScientificProduction Association Typhoon", Obninsk RUSSIA)

2.39 Safety Improvement of WER - The ENAC contribution, by D. Taylor 230

(ENAC, Brussels B) and E.L Ingham (NNC Ltd, Knutsford GB)

2.40 l&C replacements for WER 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 andN.M. Sldoruck (Institute for Nuclear Research, National Academy ofScience of Ukraine, Kiev UKRAINE)

2.42 The Dukovany NPP • the past, the present and prospects of further 241

operation, by Zdenek Llnhart and Miroslav Trnka, (NPP Dukovany,Dukovany CZ)

2.43 Experiments on the determination of WERz-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 247Russian power plants physical protection, by Alexander V. Izmallov

(Special Scientific & Production State Enterprise "Eleron",Moscow RUSSIA)

2.45 Ringha Is 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 ofNuclear Sciences Vinca, Belgrade YU)

2.50 Root cause analysis, by Olll Nevander (IVO International Ltd, Vantaa FIN) 271and 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 279at 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 Design and 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 facility and 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 equipment and 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-YvesGuena (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 actinides and 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 within AspS hard rock laboratoryin Sweden, by Anders Str&m (Swedish Nuclear Fuel and Waste 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, byE. 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. Geckels and

J.I. Kim (Karlsruhe Nuclear Research Centre, Karlsruhe D)

3.33 A versatile approach to medium term spent fuel dry storage, byJ. Uddle (GEO Alsthom Engineering systems Ltd, Leicester GB)

3.34 Underground water contamination in a spent fuel deposit, by M. Coquerelland 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

Do we need new reactors to Improve safety and economics?

4.01 EUR, the European Utility Requirements document for future LWR powerTOP 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, Bariloche ARGENTINA)

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 safety approach 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. Massler and W. Vath (KarlsruheNuclear 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 (KarlsruheNuclear 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 safety technology 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, byA. 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, by Edoardo 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 (Energy Research 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 589fuel materials for current and new reactors, by M. M. Domlnguez andL M. Mayo (ENUSA, Madrid E)

4.32 Some concepts on sodium-cooled and water-cooled reactors, by 593Dldler Costes (Paris F)