[1I05-07] Advanced LWR Development

[1I07] Development of Light Water Cooled Fast Reactor

(3)Neutronics and thermal-hydraulics characteristics in square lattice core for Pu utilization

*Junichi Miwa¹, Tetsushi Hino¹, Kazuya Ishii², Yuki Narushima¹, Noriaki Hamada¹, Hideo Soneda¹ (1. Hitachi-GE, 2. HITACHI)

Keywords:Boiling Water Reactor, Tight fuel rod lattice , Reduced moderation reactor, Pu utilization

For the purpose of Pu utilization which is a problem in the short and medium issue toward realizing a fuel cycle, the square lattice core is developed which can be realized by exchanging fuel bundles of the conventional BWR. The neutronics and thermal-hydraulics characteristics of the light water cooled fast reactor utilizing fast neutron spectrum by arranging a tight fuel rod lattice inside the square channel will be reported.