In order to permanently dispose of radioactive waste drums generated from nuclear power plants, disposal suitability must be demonstrated and the nuclides and radioactivity contained in the waste drums, including those in the shielding drums, must be identified. At present, reliable measurements of the nuclide concentration are performed using drum nuclide analysis devices at power plants and disposal facilities during acceptance inspection. The essential functions required to perform nuclide analysis using the non-destructive assay system are the correction for self-attenuation and the dead time correction. Until now, measurements have mainly been performed for drums containing solid waste such as DAW drums using SGS calibration drums with ordinary iron drums. However, for drums containing non-uniform radioactive waste, such as waste filters embedded in cement within shielding drums, a separate calibration drum needs to be produced. In order to produce calibration drums for shielded and embedded waste drums, the design considered the placement of calibration sources, setting of shielding thickness, correction for medium density, and cement mixing ratio. Based on these considerations, three calibration drums were produced. First, a shielding drum with an empty interior was produced. Second, a density correction drum filled with cement was produced to create apparent density on the surface of the shielding drum. Third, a physical model drum was produced containing a mock waste filter and cement filled in the shielding drum.

This study was conducted to identify suitable experimental conditions for the Bovine Corneal Opacity and Permeability (BCOP) assay, after which the assay was employed using 11 substances listed in the OECD test guideline (TG) 437. The opacity of the corneas was checked on days 1, 2, 3, 4, and 10 after extraction. The only day 1 showed the opacity of below 7 (limit value), which indicated the corneas have to be used in a day after extraction. The treatment time of test substances was evaluated at 3, 5, 10, 15, 20, and 30 min to determine the opacity, permeability and IVIS values. Suitable IVIS values were observed at 5, 10, and 15 min. Two culture temperature conditions, 25°C and 32°C, had similar IVIS values. The washing method suggested in the OECD TG 437 resulted in the most suitable IVIS value. Based on the established conditions, the BCOP assay was conducted using the 11 substances listed in OECD TG 437, and the sensitivity, specificity and accuracy matched those in the guidelines for all test substances. Taken together, the results of this study indicate that suitable domestic conditions for BCOP assay as an alternative eye irritation method were established. The results presented herein will be useful to future studies of other Korean alternative researches.

Recently, researches of molecular biology for the identification of root-knot nematode (RKN) species have been reported in plant quarantine. In this study, applicable and reproducible method to extract high quality genomic DNA from single nematode (Meloidogyne spp.) was developed. Also, the modified method was verified by DNA manipulation techniques such as PCR amplification and cloning. Single juvenile was floated in a drop of water and digested with proteinase K for 24 h. After that, DNA was extracted by using distilled water as extraction buffer. PCR amplification was carried out with universal primers spanning the internal transcribed spacer (ITS) region to distinguish species. When using the existing DNA detection method, quantification results showed that 42.86% of the deposited DNA was extracted. Whereas the modified DNA extraction method was increased to 100%. When PCR products test the direct sequencing using the ITS rDNA primers, it was also identified as M. javanica, M. incognita, and M. hispanica. Based on the studies conducted, the application of this modified method would be useful and efficient on plant parasitic nematode molecular assay.

원전에서 발생된 농축폐액 방사성폐기물로부터 및 를 분리 정량하기 위하여 potassium persulfate와 sulfuric acid의 산화제를 이용하는 산화증류법을 적용하였으며, 와 는 각각 기체와 HTO 액체로 순차적으로 분리되었다. 분리된 와 는 액체섬광계수기를 이용하여 계수되었고, 소광효과를 보정하여 방사능을 측정하였다. 산화증류법을 검증하기 위하여 방사성 표준물은 와 , 그리고 의 3종류, 그리고 방사성 표준물은 HTO가 이용되었다. 또한 산화되기 어려운 방향족 화합물 중 을 대상으로 가장 최적의 산화 조건을 조사하고자 황산용액 농도에 따라 FT-IR 피크 변화를 평가하였다. 방사성표준시료의 경우와 동일한 방법으로 원전 농축폐액 시료로부터 와 를 분리 검출하였는데, 그 결과 회수율은 와 가 각각 Bq/g와 Bq/g로 검출되었다.