Monday 22 March 2010

All day Plenary Session

9.00 – 9.30

Opening Session
Welcome Addresses

1. S. San Antonio, Secretary General of the European Nuclear Society

2. K. El Mediouri, Director General, CNESTEN

Session I – International Programmes
Part 1 - Chairman: E. Koonen, SCK
Co-Chairman: A. Boufraquech, CNESTEN

9.30 – 9.50

Achievement of the Moroccan Nuclear Research Centre

Marfak, T. (1)
1 - CNESTEN, Morocco

9.50 – 10.10

Chinese Programs on High Temperature Gas Cooled Reactors

Jiang, S. (1)
1 - Institute of Nuclear and New Energy Technology (INET), Tsinghua Univ., China

10.10 – 10.30

The NNSA Global Threat Reduction Initiative’s Efforts to Minimize the Use of Highly Enriched Uranium for Medical Isotope Production

Staples, P. (1)
1 - National Nuclear Security Administration (NNSA), United States

10.30 – 10.50

The Jules Horowitz Reactor Project

Iracane, D. (1); Lemoine, P. (1); Gonnier , C. (2); Bignan, G. (2)
1 - CEA Saclay, France
2 - CEA Cadarache, France

10.50 – 11.20 Coffee Break

Session I – International Programmes
Part 2 - Chairman: E. Koonen, SCK
Co-Chairman: A. Boufraquech, CNESTEN

11.20 – 11.40

Research Reactor Coalitions – Third Year Progress Report

Adelfang, P. (1); Goldman, I. (1); Alldred, K. (2)
1 - International Atomic Energy Agency, Austria
2 - International Nuclear Enterprise Group, LLC, United States

11.40 – 12.00

US PROGRESS IN LEU FUEL DEVELOPMENT

Wachs, D. (1)
1 - Idaho National Laboratory, United States

12.00 – 12.20

2010 National Progress Report on R&D on LEU Fuel and Target Technology in ARGENTINA

Cristini, P. (1); Gonzalez, A. (1); Gonzalez, R. (1); Hermida, D. (1); López, M. (1); Mirandou, M. (1); Taboada, H. (1); Blaumann, H. (1); Balart, S. (1)
1 - CNEA, Argentina

12.20 – 12.40

Foreign Research Reactor Uranium Supply Program: The Y-12 National Security Complex Process

Nelson, T. (1); Eddy, B. (2)
1 - B&W Technical Services Y-12, L.L.C., United States
2 - National Nuclear Security Administration Y-12 Site Office, United States

12.40 – 13.00

THE UNITED STATES FOREIGN RESEARCH REACTOR (FRR) SPENT NUCLEAR FUEL (SNF) ACCEPTANCE PROGRAM: 2010 UPDATE

Messick, C. E. (1); Taylor, J. L. (1); Niehus, M. T. (1)
1 - Foreign Research Reactor Spent Nuclear Fuel Acceptance Program, U.S. Department of Energy, United States

13.00 – 14.00 Lunch

Session II – Nuclear Fuel Cycle
Part 1 - Chairman: J. Wade, U.S. Department of Energy

14.00 – 14.20

Effect of the addition of a third element in gamma (U-Mo) fuel on the interdiffusion processes in U-Mo/Al and U-Mo/Al-Si systems

Allenou, J. (1); Iltis, X. (1); Charollais, F. (1); Anselmet, M. C. (1); Tougait, O. (2); Pasturel, M. (2); Lemoine, P. (3)
1 - CEA, DEN, DEC, Cadarache, France
2 - Sciences Chimiques de Rennes, UMR-CNRS, Université de Rennes, France
3 - CEA, DEN, DISN, Saclay, France

14.20 – 14.40

Swelling at the fuel edges of irradiated research reactor plates

Röhrmoser, A. (1); Petry, W. (1)
1 - Technical University Munich, FRM II, Germany

14.40 – 15.00

Parametric study of fission-induced U-Mo fuel creep and structural analysis of fuel plates in view of implications for microstructure evolution in fuel plates

Kim, Y. S. (1); Hofman, G. (1); Choo, Y. S. (1); Robinson, A. (2)
1 - Argonne National Laboratory, United States
2 - Idaho National Laboratory, United States

15.00 – 15.20

SELENIUM fuel : surface engineering of U(Mo) particles to optimise fuel performance

Van den Berghe, S. (1); Leenaers, A. (1); Detavernier, C. (2)
1 - SCK-CEN, Belgium
2 - University of Ghent, Belgium

15.20 – 15.40

Investigation of alternatives to silicon as stabilizing elements for U-Mo/Al dispersion fuel

Hofman, G. (1); Kim, Y. S. (1); Wiencek, T. (1)
1 - Argonne National Laboratory, United States

15.40 – 16.00 Coffee Break

Session II – Nuclear Fuel Cycle
Part 2 - Chairman: P. Lemoine, CEA

16.00 – 16.20

SEM Characterization of an Irradiated Monolithic U-10Mo Fuel Plate

Keiser, jr., D. (1); Jue, J.-F. (1); Robinson, A. (1)
1 - Idaho National Laboratory, United States

16.20 – 16.40

QUALIFICATION PROGRAM FOR THE RJH FUEL ELEMENTS

Anselmet, M.-C. (1); Lemoine, P.-M. (2); Koonen, E. (3); Benoit, P. (3); Gouat, P. (3); Claes, W. (3); Geens, F. (3); Brisson, S. (4); Miras, G. (4)
1 - CEA, DEN, Cadarache, France
2 - CEA, DEN, Saclay, France
3 - SCK-CEN, Belgium
4 - AREVA-TA, France

16.40 – 17.00

EPMA OF GROUND UMO FUEL WITH AND WITHOUT SI ADDED TO THE MATRIX,  IRRADIATED TO HIGH BURN UP

Leenaers, A. (1); Van den Berghe, S. (1); Charollais, F. (2); Lemoine, P. (3); Jarousse, C. (4); Röhrmoser, A. (5); Petry, W. (5)
1 - SCK•CEN, Belgium
2 - CEA-Cadarache, DEN/DEC, France
3 - CEA-Saclay, DEN/DISN , France
4 - AREVA-CERCA, France
5 - Technische Universität München, Germany

17.00 – 17.20

An assessment of safety margins for stable swelling of U-Mo alloy fuel

Rest, J. (1)
1 - Argonne National Laboratory, United States

17.20 – 17.40

SUMMARY OF ‘AFIP’ FULL SIZED PLATE IRRADIATIONS IN THE ADVANCED TEST REACTOR

Robinson, A. (1); Wachs, D. (1); Chang, G. (1)
1 - Idaho National Laboratory, United States

17.40 – 18.00

Characterization of an Irradiated RERTR-7 Fuel Plate using Transmission Electron Microscopy

Gan, J. (1); Keiser, D. (1); Robinson, A. (1); Medvedev, P. (1); Miller, B. (2)
1 - Idaho National Laboratory, United States
2 - University of Wisconsin, United States