Sunday 10 April 2005

14.00 - 17.00

Guided city walking tour,
departure from Heroes Square (Hösök tere) to the City Park

15.00 - 19.00

Registration on the mezzanine floor of the Hilton WestEnd Hotel on the Pest Side, Váci út 1-3

19.00

Transfer by coach to the conference dinner. Departure from the Hilton WestEnd Hotel

20.00 - 23.00

Conference dinner at the Budavári Fortuna Restaurant in the Castle District, Hess András tér 4

Monday 11 April 2005

07.30 - 08.30

Registration

08.30 - 08.40

Welcome Address
József Rónaky, Director General of the Hungarian Atomic Energy Authority

08.40 - 09.00

Opening Address  
Csaba Sükösd, President of the Hungarian Nuclear Society

Session 1

International Topics
- Chair: I. Vidovszky, KFKI, Hungary

09.00 - 09.20

Status report of the utilization of research reactors in the new and candidate members states of the EU
- Invited paper

I. Vidovszky, KFKI, Hungary

09.20 - 09.40

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO): General description and Implications for the research reactor infrastructure needed for R&D - Invited paper

Y. Sokolov, IAEA

09.40 - 10.00

Status, progress and plans for the Department of Energy's Global Threat Reduction Initiative

A. Bieniawski, US DOE, USA

10.00 - 10.30

Coffee break and poster viewing
Posters will be on display throughout the conference. Plenary presentation on Tuesday 12 April, 11.00 - 11.30

10.30 - 10.50

NTI points of view on the Global Threat Reduction Initiative - Invited paper

L. Holgate, NTI,  USA

10.50 - 11.10

The European Fusion Programme and the role of research reactors
- Invited paper

R. Lässer, R. Andreani, E. Diegele, EFDA Close Support Unit, Germany

11.10 - 11.30

Production of Mo 99 in Europe: Status and perspectives
- Invited paper

H. Bonet, B. David, IRE, Belgium - B. Ponsard, SCK-CEN, Belgium

11.30 - 11.50

Irradiation of fuels and materials in the Jules Horowitz reactor: The 6th European Union JHR Co-ordination Action
- Invited paper

D. Iracane, CEA Saclay, France, D. Parrat, CEA Cadarache, France

11.50 - 12.10

Status report on the cost and availability of enriched uranium for research reactors
- Invited paper

H. Müller, J. Laucht, RWE Nukem, Germany

12.10 - 12.30

Discussion

12.30 - 13.30

Buffet lunch at the Arrabona restaurant on the mezzanine floor

13.30 - 13.50

Why a fast-flux for a research reactor? The Phénix experimental programme

J. Guidez, L. Martin, J. Dumesnil, CEA VALRHO Marcoule, France

13.50 - 14.10

Business operations and decommissioning strategy for Imperial College London research reactor 'CONSORT' - A financial risk management approach

S. Franklin, Imperial College London, UK - D. Gardner, J. Mumford, R. Lea, J. Knight, PURE Risk Management, UK

14.10 - 14.20

Discussion

Session 2

Fuel development, qualification, fabrication and licensing - Chair: J. Snelgrove, ANL, USA;
co-chair: P. Lemoine, CEA, Saclay, France

14.20 - 14.40

High density U-Mo fuels - Latest results and reoriented qualification programme
- Invited paper

J. Snelgrove, ANL, USA - P. Lemoine, CEA Saclay, France - L. Alvarez, CNEA, Argentina,

14.40 - 15.00

The French U-Mo group contribution to new LEU fuel development
- Invited paper

J.M. Hamy, AREVA/
Framatome-anp, France - P. Lemoine, CEA Saclay, France - F. Huet, CEA Cadarache, France - C. Jarousse, AREVA/CERCA, France - J.L. Emin, AREVA/COGEMA, France

15.00 - 15.20

Irradiation testing of monolithic fuel at Argonne National Laboratory
- Invited paper

C. Curtis, S. Hayes, D. Wachs, M. Meyer, T. Wiencek, G. Hofman, M. Finlay, ANL, USA

15.20 - 15.30

Discussion

15.30 - 16.00

Coffee break and poster viewing
Posters will be on display throughout the conference. Plenary discussion on Tuesday 12 April, 11.00 - 11.30

16.00 - 16.20

Main results and status of the development of LEU fuel for Russian research reactors

A. Vatulin, A. Morozov, V. Suprun, I. Dobrikova, VNIINM, Russia

16.20 - 16.40

Current status of the CNEA qualification program for the fabrication of high density MTR fuel

L. Alvarez, N. Boero, J. Fabro, CNEA, Argentina

16.40 - 17.00

Post-irradiation examinations on U-Mo full-sized plate: IRIS-2 experiment

F. Huet, J. Noirot, V. Marelle, S. Dubois, CEA Cadarache, France - P. Boulcourt, P. Sacristan, S. Naury, P. Lemoine, CEA Saclay, France

17.00 - 17.20

Mechanical calculations on U-Mo dispersion fuel plates with MAIA

V. Marelle, F. Huet, CEA Cadarache, France - P. Lemoine, CEA Saclay, France

17.20 - 17.30

Discussion

17.30

Close of Day One

Tuesday 12 April 2005

Session 2

Fuel development, qualification, fabrication and licensing, continued - Chair: J. Snelgrove, ANL, USA; Co-chair: P. Lemoine, CEA, Saclay, France

08.30 - 08.50

Out of pile French research programme on the U-Mo/A system: First results

S. Dubois, F. Mazaudier, J.P. Piron, P. Martin, J. Dumas, F. Huet, CEA Cadarache, France - H. Noël, O. Tougait, University of Rennes, France - C. Jarousse, AREVA/CERCA, France - P. Lemoine, CEA Saclay, France

08.50 - 09.10

An overall estimator to assess the development of very high density fuels for research and test reactors

H. Taboada, S. Balart, M. Mirandou, M. Moscarda, CNEA, Argentina

09.10 - 09.30

Qualification of high-density aluminide fuels for the BR-2 reactor

A. Beeckmans, P. Gubel, B. Ponsard, SCK-CEN, Belgium - T. Pin, J.L. Falgoux, AREVA/CERCA, France 

09.30 - 09.40

Discussion

Sessin 3

Reactor operation, fuel safety, core conversion
- Chair: T. Van der Hagen, Delft Reactor Institute, The Netherland

09.40 - 10.00

Reduced Enrichment for Research and Test Reactors Programme: Efforts within the Global Threat Reduction Initiative

P. Staples, US DOE, USA

10.00 - 10.20

Status report on the nuclear start-up of FRM-II -  Invited paper

K. Schreckenbach,H. Gerstenberg, Munich Technical University, Germany

10.20 - 11.00

Coffee break and poster viewing
For a list of posters, see below. Plenary discussion from 11.00 - 11.30.

Posters, session 2:
Fuel development, qualification, fabrication and licensing

The analysis of effect of gaseous fission products on serviceability of various types of fuel elements used in research reactors

A. Vatulin, G. Kulakov, A. Kosaurov, I. Dobrikova, A. Morozov, VNIINM, Russia

An investigation on overcoming the interaction problem of U-Mo dispersion fuel by designing simpler monolithic U-Mo rod type fuels and adding third alloying elements to U-Mo

Y.S. Lee, C.K. Kim, K.H. Kim, J.M. Park, D.B. Lee, S.J. Oh, H.J. Ryu, D.S. Shon, KAERI, Korea

Interdiffusion between U-Mo alloys and Al or Al alloys 340°. Irradiation plan

A. Fortis,M. Mirandou, M. Ortiz, S. Balart, A. Denis, A. Moglioni, P. Cabot,  CNEA, Argentina

Irradiation and post-irradiation examination facilities in Argentina for testing of high density U compound plates

G. Ruggirello, S. Halpert, G. Estryk, J. Quintana, CNEA, Argentina

Computational and experimental analysis of causes for local deformation of research reactor U-Mo fuel pin cladddings in case of high burn-ups

V. Popov, M. Khmelevsky, IPPE, Russia - V. Lukichev, RDIPE, Russia - O. Golosov, IRM, Russia

Posters, session 3:
Reactor operation, fuel safety, core conversion, spent fuel

Evaluation of 3D energy distribution in a PWC-CCD fuel device combining thermal balance methods with MCNP & Origen-S calculation model

S. Kalcheva, Ph. Gouat, SCK-CEN, Belgium

The Valmont programme: Improved experimental techniques to support the neutronic qualification of U-Mo/AL

J.P. Hudelot, Ch. Döderlein,M. Antony, J.M. Girard, V. Laval, Ph. Fougeras, G. Willermoz, P. Leconte, CEA Cadarache, Franc

Core conversion study from silicide to molybdenum fuel in the Indonesian 30 MW multipurpose reactor GA Siwabessy (RSG-GAS)

T. Sembiring, I. Kunturo, BATAN, Indonesia

Progress of activities with regard to reconstruction of the research reactor IRT-Sofia

T. Apostolov, E. Anastasova, D. Drenski, V. Anastasov, A. Stoyanova, E. Moskov, S. Belousov, S. Kadalev, INRNE, Bulgaria - L. Manev, M. Baltiyski, Atomenergoproekt, Bulgaria

WWR-M reactor fuel elements as objects of permanent study and modernization

G. Kirsanov, K. Konoplev, . Poltavski, A. Zacharov, Petersburg Nuclear Physics Institute, Russia

CERCAs fuel elements instrumentation manufacturing.

G. Harbonnier, C. Jarousse, T. Pin, M. Febvre, P. Colomb, AREVA/CERCA, France

Burnup measurements of LEU fuel for short coding times

C. Pereda, C. Henriquez, J. Klein, J. Medel, CCEN, Chil

Posters, session 4:
Spent fuel management, back-end options, transportation

Status of the VIND programme, September 2004

M. PRsic, VINCA Institute of Nuclear Sciences, Serbia and Montenegro

New cask for irradiated rods

D. Ohayon,  P. Naigeon, AREVA/COGEMA, France

Strontium and barium precipitation as carbonates in molten eutectic LiC-KCI

C. Caravaca, G. Córdoba, M. Tomás, CIEMAT, Spai

IR-100 research reactor and proposals for spent nuclear fuel management

S. Bulkin, V.Tikhonov, V. Parabin, RDIPE, Russia - S. Smirnov, V. Podtynnykh, SNINEI, Ukraine

11.00 - 11.30

Plenary discussion of poster presentations
Chair: G. Damm, Research Center Jülich, Germany; co-chair: Ph. Beeley, Ministry of Defense, U

Session 3

Reactor operation, fuel safety, core conversion, continued
Chair: T. Van der Hagen, Delft Reactor Institute, The Netherland

11.30 - 11.50

Status of the reduced enrichment programme for FRM-II. Status 2004/05 - Invited paper

A. Röhrmoser, W. Petry, N. Wieschalla, Munich Technical University, German

11.50 - 12.10

Status of the HFR conversion and licensing

F. Wijtsma, NRG, The Netherlands

12.10 - 12.30

Review of the accident source terms for aluminide fuel: Application to the BR2 reactor

F. Joppen, SCK-CEN, Belgium

12.30 - 13.30

Buffet lunch at the Arrabona restaurant on the mezzanine floor

13.30 - 13.50

Results of out-of-pile tests of the MIR reactor irradiated fuel at high temperatures

A. Izhutov, V. Alexandrov, A. Grachev, Y. Kosvintsev, A. Novoselov, Z. Chechetkina, RIAR, Russia

13.50 - 14.10

Analysis of power peaking in HEU and LEU fuel elements on the safety behavior of FRJ-2

R. Nabbi, G. Damm, I. Neuhaus, Research Center Jülich, German

14.10 - 14.30

HEU to LEU conversion experience at the UMass-Lowell research reactor

J. White, L. Bobek, University of Massachusetts Lowell, USA

14.30 - 14.40

Discussion

Session 4

Spent fuel management, back-end options, transportation
Chair: P. Adelfang, IAEA

14.40 - 15.00

The United States Foreign Research Reactor Spent Nuclear Fuel Acceptance Programme: Proposal to modify the programme
- Invited paper

C. Messick, US DOE, USA

15.00 - 15.20

R&D for the final disposal of irradiated research reactor fuel elements

H. Curtius, H. Brücher, Research Center Jülich, Germany

15.20 - 15.50

Coffee break

15.50 - 16.10

Reprocessing U-Mo spent fuels: Dissolution experiments on non-irradiated and irradiated materials

N. Herlet, G. Ferlay, J.P. Dancausse, A. Juvenelle, CEA VALHRO Marcoule, France

16.10 - 16.30

HABOG: One building for high level waste and spent fuel in The Netherlands. The first year of experience

J. Kastelein, H.D.K. Codée, COVRA, The Netherlands

16.30 - 16.50

Spent fuel from the Finnish TRIGA research reactor in the surroundings of BWR spent fuel final disposal repository. Safety assessment and comparison to the risks of BWR fuel

S. Salmenhaara, H. Nordman, M. Anttila, VTT processes, Finland

16.50 - 17.10

Update on NAC's transportation projects

C. Anne, J. Patterson, NAC International, USA

17.10 - 17.20

Discussion

17.20

Summary and Closing Remarks - P. Gubel, SCK-CEN, Belgium, Conference Chairman

Wednesday 13 April 2005

Post ConferT

Time schedule:

• Budapest Research Reactor - Departure 09.30, return 12.30

• Budapest University Training Reactor - Departure 09.30, return 13.00

• Paks Nuclear Power Plant -  Departure 08.00, return 15.00 (lunch included)