Article ID Journal Published Year Pages File Type
1878204 Applied Radiation and Isotopes 2009 4 Pages PDF
Abstract

The biological shielding concrete of KRR-2 was activated by a thermal neutron reaction during the operation of the reactor, thus a variety of radionuclides were generated in the concrete. In order to verify the radioactivity for the final disposal of waste and to achieve a more efficient cutting of the concrete, the radioactivity inventories and distributions of the activated concrete were evaluated. The activity of gamma-emitting radionuclides was measured by using an HPGe detector. The beta-emitting radionuclides were measured by an oxidation/combustion method for 3H and 14C and a combined method of an extraction chromatography and a liquid scintillation for 55Fe and 63Ni.The dominant radioactive nuclides in the activated concrete were 3H, 14C, 55Fe and 60Co, and the maximum gamma activity was 105 Bq/g at the surface around the thermal column. The specific activities of all the nuclides were found to decrease almost linearly on a logarithmic scale along the depth from the inner surface of the concrete. Equations for scaling factors were obtained by a linear regression of logarithms from the radioactivity data of 3H/60Co, 14C/60Co and 55Fe/60Co nuclide pairs of the activated concrete. The scaling factors can be utilized for the estimation of beta radioactivity without the time consuming separation processes of the nuclides.

Related Topics
Physical Sciences and Engineering Physics and Astronomy Radiation
Authors
, , , ,