and Transport Safety Division,

In Japan, the clearance system has been in effect since December 2005, and at present, the cleared material is recycled at a site in affiliation with the nuclear installation. In the near future, it is assumed that a considerable amount of cleared material will be transported from nuclear facilities that are being decommissioned, so that the material can be recycled and used by general industry. In order to operate the clearance system with certainty, it is essential to devise a method for promptly measuring the radionuclide concentration of cleared materials that are suspected of exceeding the clearance level. That is, preparation for the contingency that an uncertain radiation source mixes with a clearance item by chance. In general, in-situ measurement of low-level radionuclide concentration is difficult since accurate information on the shape of the target, as well as on the distribution of radionuclide concentration in the target, is required. Therefore, we investigated a method for simple and rapid determination of radionuclide concentration, which does not require accurate information on the volume and density of the target. To avoid the influence of volume or density, we examined the adoption of a conversion factor with units of “(Bq/g)/cps”. ISOCS (In-situ Object Counting System) Calibratio