Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 3(1); 2005
  • Article

Journal of Nuclear Fuel Cycle and Waste Technology 2005;3(1):341-348. Published online: Mar, 30, 2005

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Sample pre-treatment for measurement of 129I in radwastes

  • Ke-Chon Choi ; Sun-Ho Han ; Kwang-Yong Jee ; Ki-Seop Choi
Abstract

Many different kinds of radwastes are discharged from the nuclear power plants, and 129I is included in these radwastes. Recovery test of 129I was evaluated for different radwastes(dry active waste, sludge, spent resin and simulated evaporator bottom). Recovery of 129I for dry active waste by acid leaching with 1.8% NaClO was 74.3%(RSD,2.2%) and 129I for spent rein by alkali fusion method with KOH as a flux agent was 87.7%(RSD,0.9%), respectively. Iodide in simulated evaporator bottom containing a high concentration of borate was adsorbed with anion exchange resin at pH 7 phosphate buffer solution. Recovery of 129I for anion exchange resin was 92.5% and not affected up to 1,200 ㎍/mL H3BO3(as a Boron). Recovery of 129I for the spent resin from nuclear power plant was 87.2% (RSD,1.2%).

Keywords

sample pre-treatment,129I,radwastes,recovery