Fuel burnup of modified fuel assembly configurations for a small medical reactor

摘要

The paper describes new designs of the fuel assembly with different types of enriched fuel for the BNCT facility with a power of 300 kW as well as criticality, neutron flux distribution and fuel burnup calculations. Since the epithermal and thermal neutron fluxes at corresponding irradiation parts were 1.6 · 10~9 n_(epi)/cm~3 and 4.5 · 10~9 nth/cm~3, it provides the best dosimetric conditions for patients within a reasonable period of time (less than 1 h).