Evaluation of the Shielding Design around the Reactor Core in the Prototype FBR Monju

Abstract

This paper describes shielding evaluation of the measurements around the reactor core ofMonju. The measurements were performed during the system start-up tests at different power levels between 0% and 45%. The measured reaction rates have been obtained radially from the core to the in-vessel storage rack and axially to the reactor vessel upper plenum. The measured values (E) were compared with the calculated values (C) obtained with the FBR shielding analysis methods. Based upon these results, the design margins around the reactor core have been reexamined and reconfirmed .