Nuclear Physics and
Related Computational Science R&D
for Advanced Fuel Cycles Workshop
Group A - NP/ASCR Needs for AFC
ABTR Core Design Summary, R. Hill, W. S. Yang, C. Grandy, Argonne National Laboratory
Material Accounting Challenges for the Advanced Fuel Cycle, Potential Nuclear Measurements and Attendant Data Needs, Alan W. Hunt, M. T. Kinlaw, S. J. Thompson, E. Reedy, D. P. Wells, J. F. Harmon, E. Farfan, J. Jones, Idaho State University
Nuclear Data Needs in Support of Advanced Fuel Cycle Research and Development
Sensitivity and Uncertainty Analysis with the ERANOS Code System, G. Aliberti, G. Palmiotti and M. Salvatores, Argonne National Laboratory
Data Needs to Support the Development of Fuel and Materials Performance Modeling and Simulation, M. Todosow, Brookhaven National Laboratory