Investigation on deformation property of waste containers for near surface disposal of low-level radioactive wastes generated from research, industrial and medical facilities

Nakata, Hisakazu ; Amazawa, Hiroya; Sakai, Akihiro ; Yamamoto, Masayuki*; Sakamoto, Yoshiaki 

The waste package, which Japan Atomic Energy Agency plans to dispose, must be satisfied the technical standard specified by Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors. One of the technical standards is that it must have enough strength to withstand the load when the waste package is disposed finally by a burial method. Japan Atomic Energy Agency is required to prove the compliance of the waste package with the technical standard. Accordingly we conducted the actual load test of waste containers and imitated waste package in order to evaluate the anti-load strength of them by collecting strain and displacement data. The test was carried out by the compression apparatus which can imitate the supposed loading condition in a concrete pit type disposal facility. Based on the loading test result, we evaluate that 200 liter drum (M-class) has a minimum strength of 18 kN and 1 m cubic container has a maximum strength of 400 kN.