NEUP CINR-19-17395: Modeling and Uncertainty Analysis of MSR Nuclear Material Accounting Methods for Nuclear Safeguards

This project will model and analyze the limits of detection for the diversion of nuclear materials from an MSR fuel cycle. We will model MSR depletion under a range of U and/or Pu diversion to quantify the resulting differences in salt composition. We will also investigate sensors to quantify fuel salt contents, and correlate the outputs with the reactor models to predict diversion detection. Results will be coupled with robust uncertainty analysis to determine limits of detection.

Additional Info

Field	Value
Awarded Institution	Pennsylvania State University
PI	William Walters