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안도희;김광락;백승우;이민수;임성팔;정흥석
- Proceedings of the Korean Radioactive Waste Society Conference
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- 2003.11a
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- pp.172-179
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- 2003
Various type of tritium wastes can be produced from nuclear fuel cycle process satisfying non-proliferation, CANDU reactors, and nuclear industry. Activities of tritium processing in the world were surveyed to develope the processing technologies of tritium wastes. The tritium wastes were classified into gas phase, liquid phase, and organic phase. And the treatment techniques for the tritium wastes are analyzed. Development of tritium processing technologies is essential to finding public acceptance of radioactive wastes and forming a solid foundation to foster the growth of nuclear industry in Korea.
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Lee, Min-Soo;Paek, Seung-Woo;Kim, Kwang-Rag;Ahn, Do-Hee;Yim, Sung-Paal;Chung, Hong-Suk;Choi, Heui-Joo;Choi, Jeong-Won;Son, Soon-Hwan;Song, Kyu-Min
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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- v.5 no.2
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- pp.155-169
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- 2007
A transport container for a 500 kCi tritium storage vessel was developed, which could be used for the transport of metal tritide from Wolsong TRF facility to a disposal site. The structural, thermal, shielding, and confinement analyses were performed for the container in a view of Type B. As a result of structural analysis, the developed container sustained its integrity under normal and accidental conditions. The maximum temperature increase of the inner storage vessel by radiation was evaluated at $134.8^{\circ}C at room temperature. In $800^{\circ}C$ fire test, The thermal barrier of container sustained the inner vessel at $405^{\circ}C after 30 min, which temperature was allowable for the container integrity since maximum design temperature of inner vessel was $550^{\circ}C. In the evaluation of the shielding, the activity of radiation was nearly zero on the outer surface of inner vessel. Consequently the transport container for a 500 kCi tritium was evaluated to pass all the safety tests including accidental condition, so it was concluded that the designed transport container is proper to be used.
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김계남;구자공;김천수
- Journal of the Korean Society of Groundwater Environment
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- v.2 no.2
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- pp.72-77
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- 1995
Flow times of the groundwater in the gneiss near Samkwang mine in Korea were estimated through the development of a mathematical model, the field hydraulic tests, and the analysis of tritium concentration of the groundwater and rainfall sampled in the study positions. Results of this study we as follows: (1) The mathematical model to calculate the age of groundwater was developed considering the tritium concentrations of rainfall precipitated in the studied area for period 1961 to 1993. (2) The ages of the groundwater in the tunnel 44, 92, 102, and 205 m below the surface were estimated at 2, 0, 4.0, 4.5, and 9.0 years, respectively. These results were verified by the data on the tritium concentrations of the groundwater in the tunnel for period 1991 to 1993.
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Kim, Jung Suk;Park, Soon Dal;Lee, Chang Hun;Song, Byong Chul;Jee, Kwang Yong
- Analytical Science and Technology
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- v.18 no.4
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- pp.298-308
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- 2005
The methods for determining C-14 and tritium contents in the spent nuclear fuel sample were developed. The carbon-14($^{14}CO_2$) released during the dissolution of the spent fuel sample and $CaCO_3$ ($CO_2$ carrier) with 8 M $HNO_3$ at $90^{\circ}C$ was collected in trap containing 1.5 M NaOH. The volatile radioactive iodine evolved when the spent fuel was dissolved, was trapped on to Ag-silicagel (Ag-impregnated silicagel) adsorbent in column which is connected to two NaOH traps. The solutions which contain tritium as HTO after fuel dissolution were decontaminated by deionization with a mixture of cation and anion exchange resins and inorganic ionexchangers. The amount of C-14 in the trap solutions and the HTO concentration in the resulting deionization water were then determined by liquid scintillation counting.
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