[1D04-07] Accident waste disposal

[1D05] Derivation of approximate analytical solutions for the nuclides release from engineered barrier system of radioactive waste disposal and understanding of response characteristics of the system

(2)Derivation of approximate analytical solution for the nuclides release from disposal facilities of pit and trench disposal system and the response characteristics

*Hirokazu Takahashi¹, Takao Ohi² (1.QJ Science, 2.Japan Atomic Energy Agency)

Keywords:Fukushima daiichi nuclear power station, Safety assessment method for radioactive disposal, Concrete pit disposal, Trench disposal, approximate analytical solution, Response characteristics of the system

Fukushima daiichi nuclear power station, Safety assessment method for radioactive disposal, Concrete pit disposal, Trench disposal, approximate analytical solution, Response characteristics of the system