NEUP CINR-25-34353: Material Accountancy Evaluation of Plutonium Content from Beryllium Fuel Forms using New Nuclear Data Measurements of Be(alpha,n)-driven Be(n,2n) Reactions

The challenge of plutonium (Pu) quantification remains a persistent challenge in nuclear material control and accountability in characterization of special nuclear material stemming from reactor fuel (FLiBe) and waste, from which large quantities of 240Pu can be registered because of the possible confounding influence of the 9Be(α,n) driven 9Be(n,2n) reaction. Neutron correlation counting techniques will be employed to measure this nuclear data reaction as foundational to advanced reactor MC&A.

Additional Info

Field	Value
Awarded Institution	Georgia Institute of Technology
PI	Shaheen Dewji