Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 4(4); 2006
  • Article

Journal of Nuclear Fuel Cycle and Waste Technology 2006;4(4):329-334. Published online: Dec, 30, 2006

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Spatial Distributions of 3H and 14C in the Shielding Concrete of KRR-2

  • Sang Bum Hong ; Hee Reyoung Kim ; Kun Ho Chung ; Mun Ja Kang ; Gyeong Hwan Jeong ; Un Soo Chung ; Jin Ho Park
Abstract

The depth distributions of total 3H and 14C activities were characterized for the activated shielding concrete from a decommissioning of KRR-2 using the commercially available tube furnace and a liquid scintillation counter. The correlation of measurement results between 3H, 14C and gammer emitter was evaluated to apply for estimating radionuclide inventory of the concrete waste generated from decommissioning KRR-2. The detection limits for 3H and 14C are 0.048 and 0.028 Bq/g respectively. The specific activities of the 3H and 14C tend to decrease exponentially as the depth of the concrete becomes deeper from the surface. In addition, the 3H and 14C activities were in good correlation with the 60Co activities analysed for the shielding concrete of KRR-2.

Keywords

3H,14C,Concrete,Activation,Decommissioning,Liquid scintillation counter