Year
2023
File Attachment
finalpaper_412_0523041000.pdf909.29 KB
Abstract
Pebble-fueled reactors (PFRs) are a category of nuclear reactors that will require accurate nuclear
material accounting and control (NMAC) measures to implement effective international
safeguards. Current concepts for NMAC measures place heavy emphasis on measuring burnup of
individual fuel pebbles to help discern pebble characteristics such as fissile material quantities.
Well-characterized data from a burnup measurement system (BUMS) could help correlate to
masses of fissile material via burnup analysis codes but this correlation may not be precise due to
pebbles experiencing a wide range of neutron fluxes and irradiation times while traversing the
reactor core via different paths. This variability in pebble trajectory and duration could lead to two
pebbles exhibiting similar fuel burnup profiles yet having different fissile material content within.
The work presented herein focuses on the justification and development of a complementary
nuclear material control (NMC) approach that could function in concert with a burnup
measurement system (BUMS) to effectively implement a combined NMAC approach for the
eventual application of international safeguards. This study first analyzed variations in fuel pebble
burnup profiles for two types of PFR designs to better understand the variability in fuel
transmutation which is based on pebble trajectories through the reactor core. Second, this study is
evaluating and experimentally verifying the applicability of candidate NMC technologies as a
complementary measure to pebble burnup measurements. The NMC approach that is discussed
herein accounts for the limitations of individual pebble identification and considers pebbles to be
classified by types and accounted for in such a manner using extrinsic and/or intrinsic features to
each pebble. An NMAC system is then discussed for eventual incorporation in future safeguarded
PFRs but further work is needed for full private industry implementation.