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ISSN : 1738-1894(Print)
ISSN : 2288-5471(Online)
Journal of Nuclear Fuel Cycle and Waste Technology Vol.9 No.3 pp.141-148
DOI :

Detennination of 129I in simulated radioactive wastes using distiIlation technique

Ke Chon Choi1),Byung Cheol Song,Sun Ho Han,Yong Joon Park,Kyuseok Song
Korea Atomic Energy Research Institute, 1045 Daedeok-daero,Yuseong,Daejeon,Korea
1) Corresponding Author. E-mail: nkcchoi@kaeri.re.kr

Abstract

It is clarified in the radioactive waste transfer regulation that the concentration of radioactive waste for the major radio nuclide has to be examined when radioactive waste is guided to the radioactive waste stores. In case of the low level radioactive waste sample, the analytical results of radioactive waste concentration frequently show a value lower than minimum detectable activity (MDA). Since the MDA value basically depends on the amount of a sample,background value, measurement time, counting efficiency, and etc, it would be necessary to increase a sample amount with a intention of minimizing MDA. In order to measure a concentration of 129I in low and medium level radioactive waste, 129I was collected by using a distillation technique after leaching the simulated radioactive waste sample with a non-volatile acid. The recovery of 129I measured was compared with that measured with column elution technique which is a conventional method using an anion-exchange resin. The recovery of inactive iodide by using the distillation method and column elution were found as 86.5 0.9% and 87.3 2.7%, respectively. The recovery and MDA value calculated for distillation technique when 100 g of extracted solution of 129I was taken,were found to be 84.6 1.6% and 1.2 10-4 Bq/g, respectively. Consequently, the proposed technique with simplified process lowered the MDA value more than 10 times compared to the column elution technique that has a disadvantage of limited sampling amount.

종류법을 이용한 모의방사성폐기물 중 1291의 정량

최계천1),송병철,한선호,박용준,송규석
한국원자력연구원， 대전시 유성구 대덕대로 1045

초록

방사성폐기물이 처분장에 인도 될 때 주요 방사성 핵종의 방사능 농도를 규명 하도록 방사성폐기물 인도 규정에 명시되어 있다. 저준위 방사성폐기물 시료의 경우 측정된 방사능 농도가 최소검출 방사능 농도(MDA: Minimum dectable activity) 이하의 값을 나타낼 경우가 많으며, MDA는 시료의 양, 바탕 값, 계측시간 및 계측효율 등에 따라서 달라지므로 MDA를 낮추기 위하여 가능한 많은 양의 시료를 취할 필요가 있다. 모의 잡고체 시료에 첨가된 요오드의 회수율을 결정하기 위한 방법으로서 모의 시료 중 비 방사성 요오드를 비휘발성 산으로 침출시킨 후 침출액을 직접 증발시키는 방법과 음이온 교환수지를 이용하여 I-를 흡착하여 분리하는 칼럼용리방법으로 측정하여 회수율을 비교한 결과, 증류법과 칼럼용리방법의회수율은 각각 86.5±0.9%, 87.3±2.7%로 나타났다. 증류법에 의한 모의 방사성 시료 중 129I 요오드의회수율 및 MDA는 84.6±1.6%, 1.2×10-4 Bq/g로 각각 나타났으며, 분리공정을 단순화하고 많은 양의 시료를 취함으로써, 칼럼용리 방법의 단점을 보완하고 10배 이상 MDA를 낮출 수 있는 결과를 얻을 수 있었다.

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