• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.19 no.2
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• pp.177-186
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• 2021

Radioactive materials from nuclear power facilities can be released into the atmosphere through various channels. Recently, the dispersion of radioactive materials has become critical issue in Korea after Kori Unit 1 and Wolsong Unit 1 were permanently shut down. In this study, annual atmospheric dispersion factors were compared based on the continuous release and purge release using the XOQDOQ computer program, a method for calculating atmospheric dispersion factors at commercial nuclear power stations. The meteorological data analyzed in this study was based on the Shin Kori nuclear power meteorological tower which has the largest operating nuclear power plants in Korea, for three years (from 2008 to 2010). The analysis results of the dispersion factor of the radioactive material release obtained using the XOQDOQ program showed that the difference between the continuous release and purge release was within two times. This study will be valuable helpful for revealing the uncertainty of the predictive atmospheric dispersion factor to achieve regulation.

• Korean Journal of Food Science and Technology
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• v.38 no.6
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• pp.738-741
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• 2006

Volatile flavor compounds in commercial sterilized milk were analyzed and identified by static headspace, purge-and-trap, and solid-phase microextraction (SPME) methods. About 20 volatile compounds were identified by GC/MS, and aldehydes and ketones were the most distinctive and abundant compounds. Static headspace analysis allowed the identification of only the most abundant compounds, such as acetone. Five ketones (acetone, 2-butanone, 2-pentanone, 2-heptanone, 2-nonanone), four aldehydes (2-methylbutanal, pentanal, hexanal, benzaldehyde) and dimethyl sulfide, all of which were responsible for off-flavor in milk, were found by the purge-and-trap and SPME methods. The two methods differed little in their release of these compounds, but they yielded different amounts in the extraction.

• Korean Journal of Microbiology
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• v.36 no.1
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• pp.52-57
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• 2000

A method for quantitative and qualitative analysis of geosmin, odorant produced by several actinomycetes and cyanobacteria, was established and optimized. The effects of environmental conditions on the growth of Phormidium sp. NIVA-CYA7 were examined and the production and release of geosmin by the species was analyzed by using the purge and trap-gas chromatographic technique. One of the major advantages of the technique established in the present study is that the preparation of sample is simpler and purge time is shorter. Under the culture conditions (pH 7.9, $20^{\circ}C$, 120-140 $\mu$E/$m^2$/s and Z8 medium), Phormidium showed growth characteristics with a lag phase for 8 days and an exponential phase for 14 days followed by a stationary phase. Reduction of inorganic nitrogen concentrations in the culture medium from 250 to 100 or 25 $\mu$M brought no significant effect on the cell growth. However, the cell growth was significantly inhibited with decreasing concentrations of inorganic phosphorus from 25 to 10 or 2.5 $\mu$M. When the inorganic phosphorus concentration in the medium was lowered from 25 to 10 $\mu$M, the levels of geosmin in the organism expressed as percentages per unit TOC and chlorophyII-$\alpha$ increased by 35% and 68%, respectively. When the initial pH of the medium was 9.4, geosmin content was 0.0824 $\mu$g/mg C, which was 2-fold higher than that at pH 7.9 Consequently, the level of geosmin in Phormidium was found to vary with growth phases of the culture, external inorganic phosphorus concentration and external pH, while the release of geosmin was not significantly affected by the factors.

• Nuclear Engineering and Technology
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• v.56 no.1
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• pp.106-113
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• 2024

Understanding the tritium release and retention behavior of candidate tritium breeder materials is crucial for breeder blanket design. Recently, a melt spraying process was developed to prepare Li₄SiO₄ pebbles, which were subsequently subjected to the in-pile tritium production and extraction platform in China Mianyang Research Reactor (CMRR) to investigate their in-situ tritium release behavior and irradiation performance. The results demonstrate that HT is the main tritium release form, and adding hydrogen to the purge gas reduces tritium retention while increasing the HT percent in the purge gas. Post-irradiation experiments reveal that the irradiated pebbles darken in color and their grains swell, but the mechanical properties remain largely unchanged. It is concluded that the tritium residence time of Li₄SiO₄ made by melt spraying method at 467 ℃ is approximately 23.34 h. High-density Li₄SiO₄ pebbles exhibit tritium release at relatively low temperatures (<600 ℃) that is mainly controlled by bulk diffusion. The diffusion coefficient at 525 ℃ and 550 ℃ is 1.19 × 10^-11 cm²/s and 5.34 × 10^-11 cm²/s, respectively, with corresponding tritium residence times of 21.3 hours and 4.7 hours.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.117-123
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• 2003

In succession to the previous paper, the tritium injection system and the regeneration system of the tritium handling system are presented. Both systems should be placed inside glove boxes since there can be potential leakage of tritium from these systems. The tritium injection system should be capable of measuring the exact amount of the injected tritium to keep track of the tritium inventory. The tritium injection system is designed to recover the remaining tritium from the system after injection for the minimization of tritum release to the environment as well as for the recovery of precious resource. TRS equipment such as MS, Ni catalyst bed, and metal getter are regenerated with a standalone regeneration system. Unlike other equipments which can be regenerated by heating and purging with appropriate gas, regeneration of the metal getter used to recover tritium is somewhat complicated.