SUBJECT: M.S. Thesis Presentation
BY: Evan Redd
TIME: Wednesday, March 25, 2015, 8:30 a.m.
PLACE: Boggs, 3-39
TITLE: X-10 Reactor Forensic Analysis and Evaluation Using a Suite of Neutron Transport Codes
COMMITTEE: Dr. Anna Erickson, Chair (NRE)
Dr. Glenn Sjoden (AFTAC)
Dr. Kevin Manalo (HPC)
Dr. Ce Yi (NRE)


The X-10 production reactor that aided our country's first weapons campaign will be modeled and analyzed based on data available from open literature. Results will be compared to previous ORIGEN results and analytical measurements available from the open literature, as required. 3-D burnup analysis will also be completed using selected neutron transport code packages, and will readily enable the reporting of fission products and actinides in the 3-D core using deterministic and Monte Carlo transport results. It is anticipated that these results should highlight distinct characteristics and forensic signatures of early production reactors. This project will facilitate assessment of the predictive capabilities of these advanced codes, and will enable other researchers to tap into actinide and fission product data represented in a full-scale 3-D model.