• Korean Chemical Engineering Research
• /
• v.50 no.4
• /
• pp.595-603
• /
• 2012

International Thermonuclear Experimental Reactor (ITER) will be constructed in 2019 according to the JIA (Joint Implementation Agreement) of 7 countries. The ITER fusion fuel cycle consists of fusion vacuum vessel, tritium plant and fuelling system. The tritium plant provides the functions of storage, delivery, separation, removal and recovery of the deuterium and tritium used as fusion fuels for the ITER. The tritium plant systems supply deuterium and tritium from external sources and treat all tritiated fluids from ITER operation through Storage and Delivery System (SDS), Tokamak Exhaust Processing (TEP), Isotope Separation System (ISS), Water Detritiation System & Atmosphere Detritiation System (WDS & ADS) and Analysis System (ANS). In this paper, the functions and design requirements of the major systems in the tritium plant and the status of R&D are described. Korean party is developing the SDS for ITER tritium plant and partially attaining the WDS technology through the construction and operation experience of the Wolsong Tritium Removal Facility (WTRF). Now it is expected that researchers in other fields such as chemical engineering take part in the development of upcoming technologies for ISS and TEP.

• 대한방사선방어학회:학술대회논문집
• /
• 2009.04a
• /
• pp.112-113
• /
• 2009

원전주변 환경방사능측정 시료 중 다른 시료와 다르게 저수지는 방사능축적 경향을 확인할 수 있는 가능성이 매우 높다. 본 논문에서는 문제해석의 단순화를 위해 여러 가정의 전제하에 원전주변 저수지의 삼중수소농도계산이 가능한 수치모델을 제안하고 그 결과를 통해 환경방사능 해석에 필요한 값들을 제공하는 방법을 제안하였다. 환경방사능 해석에 제공될 수 있는 값들로는 저수지의 삼중수소농도의 포화여부, 저수지 인근의 삼중수소 농도, 원전으로부터 삼중수소 방출율의 추정, 저수지에 대한 모니터링의 필요성 등이 포함된다.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
• /
• 2006.04a
• /
• pp.286-288
• /
• 2006

삼중수소는 물분자중 수소원소의 동위원소로서 물의 유동연구에 가장 이상적인 추적자로서 활용된다. 이러한 삼중수소 분석결과는 지표수 지하수 상관관계 해석 및 지하수의 연대측정등 수문학 연구의 중요한 자료로 활용되고 있다. 지하수 연구에 필요한 삼중수소의 측정법을 확립코자 극저준위 액체섬광계수기를 도입하였으며 NIST 표준시료를 사용하여 실험방법을 확립하였다. 삼중수소의 측정효율은 25.7 % 였으며, 전기분해법을 사용하지 않고 단순 분리법만을 사용하였을 경우 10 ml의 측정 시료와 섬광액으로 Ultima-Gold LLT를 사용하여 0.18 Bq(1.5 TU)의 검출한계를 얻었다.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2003.11a
• /
• pp.539-543
• /
• 2003

The objective of this to improve the reliability of the safety evaluation code for Wolsong Tritium Removal Facility(WTRF) which is on the development for environmental assessment. To achieve this, tritium concentrations calculated in the Wolsong Units of this study are compared with that of the existing reference. As the result, the tritium concentration in each Wolsong nuclear power plant unit just before operating WTRF is 60.9Ci/kg, 36.3Ci/kg, 30.0Ci/kg, 26.5Ci/kg under the assumption that the WTRF begins operation in 2005, respectively. This result is almost same with that of the existing reference. But the reducing rate of tritium concentration in the moderator is faster than that of the reference result Finally it is expected to drop below 10Ci/kg after WTRF operation. And this result is also similar with that of the existing reference.

• Journal of the Korean Society of Groundwater Environment
• /
• v.6 no.3
• /
• pp.126-132
• /
• 1999

Tritium. a radioisotope of hydrogen, is a constituent of water molecules and, therefore. is a ideal water tracer in hydrology. The tritium level of the precipitation in Korea has been monitored at the Pohang station from 1961 to 1976 by IAEA and has been analyzed from 1987 to present by KAERI. The tritium contents of the precipitation were recorded up to about 1,940 TU owing to world-wide nuclear testing in 1963. The contents have decreased and in present are about 10 TU. of which values are similar to those in pre-thermonuclear period. These data can be usefully applied to hydrological studies such as interpretation of relationship between groundwater and surface water and dating of groundwater.

• Journal of Korean Society for Atmospheric Environment
• /
• v.3 no.1
• /
• pp.27-33
• /
• 1987

The environment and biological studies of tritium have been carried out in the advanced countries since the mid 1950's. In the case of a potential tritium exposure, the usual procedure is trifium bioassay (as HTO) in human urine in order to determine the amount of tritium deposited in the body called tritium body burden. The maximum permissible body burden(MPBB) of tritium in total body is about $30{\mu}Ci/{\ell}$ for body tissue. In the bioassay, the most common investigation level for detection of tritium in urine is 1/10th of MPBB. For this bioassay project, the first priority is given to obtaining a quench correction curve. This consideration is necessary because of the variability in color of human urine specimens. Quenching effect in this case mainly is caused by the absorption of scintillation light flashes by the urine sample. By the least squares method on the statistical basis, an estimated formula for quench correction curve was determined to be Y = 0.771 + 1.836 ${\tmes}10^{-4}$X, where the efficiency(Y) was ranged from about 12% to 31% in the liquid scientillation counting. In this paper, a brief theory concerning the biological half-life of tritium and the retention formula to apply to systematically distributed tritium are described.

• Journal of Radiation Protection and Research
• /
• v.34 no.2
• /
• pp.87-94
• /
• 2009

Tritium is the one of the dominant contributors to the internal radiation exposure of workers at pressurized heavy water reactors (PHWRs). This nuclide is likely to release to work places as tritiated water vapor (HTO) from a nuclear reactor and gets relatively easily into the body of workers by inhalation. Inhaled tritium usually reaches the equilibrium of concentration after approximately 2 hours inside the body and then is excreted from the body with a half-life of 10 days. Because tritium inside the body transports with body fluids, a whole body receives radiation exposure. Internal radiation exposure at PHWRs accounts for approximately 20-40% of total radiation exposure; most internal radiation exposure is attributed to tritium. Thus, tritium is an important nuclide to be necessarily monitored for the radiation management safety. In this paper, metabolism for tritium is established using its excretion rate results in urine samples of workers at PHWRs and an effective half-life, a key parameter to estimate the radiation exposure, was derived from these results. As a result, it was found that the effective half-life for workers at Korean nuclear power plants is shorter than that of International Commission on Radiological Protection guides, a half-life of 10 days.

• Journal of Radiation Protection and Research
• /
• v.40 no.4
• /
• pp.267-276
• /
• 2015

Several analyses on tritium that is the largest release of gas or liquid radioactive waste from domestic PWR and PHWR NPPs were carried out, such as release comparison, directional frequency of wind and tritium behavior changes in environmental samples. First of all, analysis result showed that tritium released from PHWR was more than ten times as gas and double to three times as liquid in comparison to PWR in 2013. Independent release management in NPP units is needed to precisely control and analyze tritium, since there were 2 units of some NPPs having the same amount of release during analysis. In analysis on frequency of wind direction, average range showed 1.7 to 11.5% by 16-point compass. In case of analysis on sampling points by wind direction, Result showed most of the sampling points are right in places. However, There are some areas needed to examine. In analysis on tritium concentration changes in environmental samples, tritium concentration near NPPs was higher than one far away from NPPs. In case of environmental samples far from PWR, a trace of tritium occur. While, tritium concentration near NPPs was more than or equal to one further from PHWR. In conclusion, tritium occurs considerably in PHWR and is lower than standard in samples. but, it is still detected. Therefore, it is needed to strengthen control in system in NPPs and to consistently monitor tritium in environment.

• Journal of Radiation Protection and Research
• /
• v.17 no.2
• /
• pp.25-35
• /
• 1992

To evaluate tritium level in some environmental samples, tissue-free water tritium (TFWT) and tissue-bound tritium (TBT) were analyzed in rices, chinese cabbages and pine needles collected at 12 locations in Korea. The TFWT was recovered by freeze-drying of the samples and the TBT was obtained in the form of water by combustion of the dried samples. Tritium was measured by liquid scintillation counter. The concentrations of TFWT were in the range of $0.96{\sim}3.96 Bq/1,\; 0.83{\sim}3.40 Bq/1\;and\;1.02{\sim}3.01 Bq/1$ in rices, chinese cabbages and pine needles, respectively. The mean specific activity ratios (TBT/TFWT) were 0.94, 1.71 and 1.39 in rices, chinese cabbages and pine needles, respectiviely. This excess TBT in the samples may be attributed to the fact that the residence time of TBT in the plant is longer than that of TFWT. The specific activity ratio depends on the plant species, the exposed time to tritiated atmosphere, atmospheric moisture, temperature and diffusion factor.

• Journal of Radiation Protection and Research
• /
• v.22 no.2
• /
• pp.97-101
• /
• 1997

During the period of March 1995 to December 1995, tritium concentrations of tritiated water vapor (HTO) and tritiated hydrogen (HT) in the atmosphere in Taejon were measured to evaluate present background levels of tritium in the atmosphere. Air samples were collected continuously for three weeks with a sampling system for tritium in the atmosphere and were analyzed by a liquid scintillation counting system. The range of the atmospheric HTO concentrations was 3.2-36 mBq $m^{-3}$ with a mean value of 16.2 mBq $m^{-3}$. The atmospheric HTO concentrations were the highest in summer and the lowest in winter. This trend was similar to the variation of atmospheric absolute humidity. The specific activities of tritium in atmospheric water vapor in Taejon ranged from 0.62 Bq $L^{-1}$ to 3.82 Bq $L^{-1}$ with a mean value of 2.04 Bq $L^{-1}$. The atmospheric HT concentrations were in the range of 35.7 mBq $m^{-3}$ to 48.9 mBq $m^{-3}$ with a mean value of 41.1 mBq $m^{-3}$.