Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 17(1); 2019
  • Article

Journal of Nuclear Fuel Cycle and Waste Technology 2019;17(1):121-126. Published online: Mar, 30, 2019

Inventory Estimation of 36Cl and 41Ca in Concrete of Kori Unit 1

  • Mee Jang ; Jong Myoung Lim ; Hyun Chul Kim ; Chang-Jong Kim
Abstract

The radionuclide inventory prediction of a nuclear power plant can help establish decommissioning plan by providing information of radiation environment. Accumulated radionuclides in reactors and related facilities after reactor shutdown can be divided into neutron activated materials and contaminated materials. Among the neutron activated radionuclides, 36Cl and 41Ca are important from the viewpoint of disposal because of its long half-life and physiochemical characteristics. In this research, we calculated the radionuclides of 36Cl and 41Ca in bioshielding concrete by estimating the neutron flux and cross section using the MCNPX. And we evaluated the inventories of 36Cl and 41Ca using the activation calculation code ORIGEN2.

Keywords

Bioshielding concrete,Radionuclide inventory,36Cl,41Ca