1. OECD-NEA Workshop on Criticality Safety Research Needs for Future Nuclear Systems J. Blair Briggs David W. Nigg Idaho National Laboratory (INL) George Imel Idaho State University (ISU)

2. 2 Location: Idaho State University

3. 3 WPNCS & Associated Expert Groups – Schedule Workshop on Criticality Safety Research Needs for Future Nuclear Systems September 21 – 22, 2009 Expert Group on Burnup Credit September 23, 2009 Expert Group on Source Convergence September 24, 2009 (AM) Expert Group on Criticality Excursion Analysis September 24, 2009 (PM) Working Party on Nuclear Criticality Safety September 25, 2009

4. 4 OECD-NEA Workshop on Criticality Safety Research Needs for Future Nuclear Systems September 21-22 2009, Idaho Falls, Idaho

5. 5 Workshop on Criticality Safety Research Needs for Future Nuclear Systems Six Plenary Sessions with only Invited Papers Panel Discussion – Questions from Participants Summary and Conclusions

6. 6 Draft Agenda Opening Remarks – Purpose and Goals of the Workshop SESSION I: State of the art of criticality safety studies for current nuclear fuel cycle development –Speaker 1: –Speaker 2: –Speaker 3: –Speaker 4: Session II: Status of development of innovative fuel cycle for future nuclear energy system (AFCI, GEN-IV, ADS,…) Fuel fabrication and transportation issues associated with innovative nuclear systems and fuel cycles. Innovative reprocessing methods & associated criticality safety issues, including handling of large quantities of higher actinides. –Speaker 1: Terry Todd, INL – AFCI Separations Development –Speaker 2: Kemal Pasamehmetoglou, INL – AFCI Fuel Development –Speaker 3: Temitope Taiwo, ANL – AFCI Systems Analysis –Speaker 4: Jon Carmac, INL – Fuel Performance & Design –Speaker 5: Bob Hill, ANL – AFCI Fast Reactor Development / GEN-IV Reactor Development –Speaker 6: Jesse Gehin, ORNL – AFCI Systems Analysis –Speaker 7: Steve Johnson – Space Nuclear Systems –Speaker 8: Session III: Criticality safety studies for future nuclear fuel cycles Validation of Computational methods via integral experiments. Needs for new integral experiments. Needs for Improved Differential Nuclear Data for GNEP Criticality Safety Applications –Speaker 1: Richard McKnight, ANL –Speaker 2: –Speaker 3: –Speaker 4:

7. 7 Draft Agenda Opening Remarks – Purpose and Goals of the Workshop SESSION I: State of the art of criticality safety studies for current nuclear fuel cycle development –Speaker 1: –Speaker 2: –Speaker 3: –Speaker 4: Session II: Status of development of innovative fuel cycle for future nuclear energy system (AFCI, GEN-IV, ADS,…) Fuel fabrication and transportation issues associated with innovative nuclear systems and fuel cycles. Innovative reprocessing methods & associated criticality safety issues, including handling of large quantities of higher actinides. –Speaker 1: Terry Todd, INL – AFCI Separations Development –Speaker 2: Kemal Pasamehmetoglou, INL – AFCI Fuel Development –Speaker 3: Temitope Taiwo, ANL – AFCI Systems Analysis –Speaker 4: Jon Carmac, INL – Fuel Performance & Design –Speaker 5: Bob Hill, ANL – AFCI Fast Reactor Development / GEN-IV Reactor Development –Speaker 6: Jesse Gehin, ORNL – AFCI Systems Analysis –Speaker 7: David Petti, INL – NGNP –Speaker 8: Session III: Criticality safety studies for future nuclear fuel cycles Validation of Computational methods via integral experiments. Needs for new integral experiments. Needs for Improved Differential Nuclear Data for GNEP Criticality Safety Applications –Speaker 1: Richard McKnight, ANL –Speaker 2: –Speaker 3: –Speaker 4:

8. 8 Draft Agenda (Continued) Session IV: Direct disposal of spent nuclear fuels (BUC, Assay Data, codes validation ) –Speaker 1: Phil Wheatley, INL –Speaker 2: John Wagner, ORNL –Speaker 3: –Speaker 4: Session V: Other topics related with current systems and expectations on progress of their the fuel cycle Increased enrichment of 235U beyond 5wt% New type of burnable poisons using erbium or possible other materials Retrieval, repackaging, transportation, long-term surface storage and disposal of Legacy Waste. –Speaker 1: Ronaldo Szilard, INL –Speaker 2: –Speaker 3: –Speaker 4: Session VI: Bias and Uncertainty Analysis for Criticality Safety Assessment, current situation and expectations –Speaker 1: Tatiana Ivanova –Speaker 2: Anatoli Tsiboulia –Speaker 3: –Speaker 4:

9. 9 Draft Agenda (Continued) Session VII: Panel Discussion Possible Future Activities Related to Advancing the Field of Criticality Safety for Future Nuclear Fuel Cycle Systems Under OECD/NEA/NSC Recommendations to the NSC –Panel Member 1: –Panel Member 2: –Panel Member 3: –Panel Member 4: –Panel Member 5: –Panel Member 6: Session VIII: Summary and Conclusions