[3D06-09] Pu-Thermal Reactor

11:20 AM - 11:35 AM JST(2:20 AM - 2:35 AM UTC)

[3D08] Future prospects of advanced pluthermal operation for BWR based on domestic reprocessing(3) Utilization scenarios of light-water-cooled fast reactor (RBWR)

*Sota Araki¹, Tetsushi Hino^1,2, Kenichi Yasuda² (1. Hitachi, 2. HGNE)

Keywords:

pultonium thermal operation,BWR,RBWR

Hitachi/Hitachi-GE is developing a light-water-cooled fast reactor, RBWR, taking advantage of the features of BWR, in which the coolant (neutron moderator) boils. Currently, Hitachi/Hitachi-GE is focusing on the development of the RBWR with a square lattice fuel (square lattice RBWR), which assumes to be back-fitted to existing BWR plants and use of MOX pellets within the enrichment range supplied from the Rokkasho MOX fuel fabrication plant. The square lattice RBWR aims to reduce the volume of spent fuel by promoting the use of plutonium and the Rokkasho reprocessing plant as well as to contribute to a smooth transition to the fast reactor cycle. In this presentation, the development status and aims of the square lattice RBWR will be detailed.