Transactions

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.C. 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 

09.40 - 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

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

11.30 - 11.50

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

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

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

14.30 - 14.50

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

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

14.40 - 15.00

Foreign Research Reactor Spent Nuclear Fuel Acceptance Programme: Proposal to modify the programme

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

15.50 - 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

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

The analysis 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 regard 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, Chile

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

Status of the VIND programme, September 2004

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

New cask design for transportation of 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, Spain

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

S. Bulkin, V.Tikhonov, V. Parabin, RDIPE, Russia - S.B. SMIRNOV, V.N. PODTYNNYKH, SNINEI, Ukraine