[2G01-04] Sodium-cooled fast reactor 1

10:15 AM - 10:30 AM JST(1:15 AM - 1:30 AM UTC)

[2G04] Development of an innovative small sodium-cooled fast reactor(21) Geological disposal of high-level radioactive waste from pyroprocessing

*Tomofumi Sakuragi¹, Hidekazu Asano¹, Shingo Tanaka¹, Miki Harigai¹, Yuma Sekiguchi², Daisuke Watanabe³ (1. RWMC, 2. CRIEPI, 3. HGNE)

Keywords:

Sodium-cooled fast reactor,Metal fuel,Pyroprocessing,High-level radioactive waste,Glass-bonded sodalite,Geological disposal

For implementation of future fast reactor cycle system, we are currently studying a small sodium-cooled fast reactor using metallic fuel. In this system, it is assumed that spent metallic fuel will be pyroprocessed to recycle actinides, and high-level radioactive waste containing fission products will be immobilized in glass-bound sodalite and disposed of in a geological repository. In this study, we investigated the repository footprint and long-term safety after disposal based on the radionuclides inventory and the heat generation characteristics of glass-bound sodalite. We then compared it with the high-level radioactive waste (vitrified waste) from light-water reactors and wet reprocessing, and examined its compatibility with conventional disposal concepts. We also summarize future technical issues for pyroprocessing and waste synthesis in the context of final disposal.