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Appl Radiat Isot. 2013 Sep;79:109-13. doi: 10.1016/j.apradiso.2013.04.027. Epub 2013 May 13.

The radioactivity estimation of 14C and 3H in graphite waste samples of the KRR-2.

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1
Ulsan National Institute of Science and Technology, Ulsan 689-798, Republic of Korea. kimheere@hanmail.net

Abstract

The radioactivity of (14)C and (3)H in graphite samples from the dismantled Korea Research Reactor-2 (the KRR-2) site was analyzed by high-temperature oxidation and liquid scintillation counting, and the graphite waste was suggested to be disposed of as a low-level radioactive waste. The graphite samples were oxidized at a high temperature of 800 °C, and their counting rates were measured by using a liquid scintillation counter (LSC). The combustion ratio of the graphite was about 99% on the sample with a maximum weight of 1g. The recoveries from the combustion furnace were around 100% and 90% in (14)C and (3)H, respectively. The minimum detectable activity was 0.04-0.05 Bq/g for the (14)C and 0.13-0.15 Bq/g for the (3)H at the same background counting time. The activity of (14)C was higher than that of (3)H over all samples with the activity ratios of the (14)C to (3)H, (14)C/(3)H, being between 2.8 and 25. The dose calculation was carried out from its radioactivity analysis results. The dose estimation gave a higher annual dose than the domestic legal limit for a clearance. It was thought that the sampled graphite waste from the dismantled research reactor was not available for reuse or recycling and should be monitored as low-level radioactive waste.

KEYWORDS:

Annual dose; Disposal; Graphite; KRR-2; LSC; Radioactivity of (14)C and (3)H

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