• Title/Summary/Keyword: Tritium Removal Facility

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PREDICTION OF THE TRITIUM CONCENTRATION IN THE SOIL WATER AFTER THE OPERATION OF WOLSONG TRITIUM REMOVAL FACILITY

  • CHOI HEUI-JOO;LEE HANSOO;SUH KYUNG SUK;KANG HEE SUK
    • Nuclear Engineering and Technology
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    • v.37 no.4
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    • pp.385-390
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    • 2005
  • The effect of the Wolsong Tritium Removal Facility on the change of tritium concentration in the soil water was assessed by introducing a dynamic compartment model. For the mathematical modeling, the tritium in the environment was thought to come from two different sources. Three global tritium cycling models were compared with the natural background concentration. The dynamic compartment model was used to model the behavior of the tritium from the nuclear power plants at the Wolsong site. The source term for the dynamic compartment model was calculated with the dry and wet deposition rates. The area around the Wolsong nuclear power plants was represented by the compartments. The mechanisms considered in deriving the transfer coefficients between the compartments were evaporation, runoff, infiltration, hydrodynamic dispersion, and groundwater flow. We predicted what the change of the tritium concentration around the Wolsong nuclear power plants would be after future operation of the tritium removal facility to show the applicability of the model. The results showed that the operation of the tritium removal facility would reduce the tritium concentration in topsoil water quickly.

Optimum Design of the Wolsong Tritium Removal Facility

  • Ahn, Do-Hee;Lee, Han-Soo;Chung, Hong-Suk;Song, Myung-Jae;Son, Soon-Hwan
    • Nuclear Engineering and Technology
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    • v.28 no.4
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    • pp.415-422
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    • 1996
  • Tritium removal from tritiated heavy water in a PHWR is the most effective way in reducing workers' internal dose and radioactivity emissions from Wolsong NPP. The optimum design of the Wolsong TRF (Tritium Removal Facility) was carried out using an approximate short-cut method with an assumption that the TRF, designed to extract 8 MCi per year of elemental tritium from a heavy oater feedstream, uses Liquid Phase Catalytic Exchange (LPCE) front-end process and Cryogenic Distillation (CD) process.

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Evaluation of Time Dependent Tritium Concentration for Safety Analysis in Wolsong Tritium Removal Facility (월성 삼중수소 저장 시설 안전성 평가를 위한 시간에 따른 삼중수소 농도 평가)

  • 육대식;이건재;정흥석
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.539-543
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    • 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.

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Parametric Analysis of Design Capacity for Tritium Removal Facility

  • 손순환;정양근;이철언
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05b
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    • pp.250-255
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    • 1997
  • 중수로형(PHWR) 원자력발전소는 감속재와 냉각재로 중수를 사용하고 있어 방사성 수소동위원소인 삼중수소 생성량이 경수로에 비해 크며 계통내 삼중수소 축적량은 운전년수에 따라 증가하게 된다. 중수로형 원전에서 삼중수소 저감화를 위한 장기 대책으로 Tritium Removal Facility를 적용하는 경우, 우선적으로 괴려하여야 할 사항은 적절한 TRF의 용량을 결정하는 것이다. 이는 초기 시설 투자비뿐만 아니라 설비 및 운전의 신뢰도와 이용율에도 영향을 미치므로 연속운전이 가능하도록 용량을 결정하는 것이 중요하다. 이를 위해 감속재를 대상으로 삼중수소 농도 목표치, 삼중수소 농도 목표치 도달기간, 탈 삼중수소율, TRF 적용시점이 TRF 처리량과 촉매탑 높이에 미치는 영향을 분석하였다. 삼중수소 농도 목표치는 5~15Ci/kg, 도달기간은 3~8년, 탈 삼중수소율은 0.05~0.4, TRF 적용시점은 가동 후 10~20년이 적절한 것으로 확인되었다.

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수소동위원소의 회분식 저장특성

  • 백승우;안도희;김광락;이민수;임성팔;정흥석
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.247-247
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    • 2004
  • 가압 중수로형 원자력발전소에서는 원자로의 감속재 및 냉각재로 사용하는 중수(heavy water)로 인한 삼중수소(tritium)의 생성이 전체 방사선 준위 상승의 가장 중요한 원인이 되고 있다. 따라서 4기의 중수로가 운전 중인 우리나라에서도 월성원자력 발전소에 삼중수소 제거 설비(Tritium Removal Facility)가 건설 중에 있다. 이 시설로부터 99% 이상의 순도인 삼중수소가 회수되며, 회수된 삼중수소는 장기적인 저장을 위하여 안전하게 포장되어야 한다.(중략)

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A Study on the Environment and Human Tritium Radiation Monitoring around the Heavy Water Nuclear Power Plant (중수로 원전 주변 환경 및 인체 삼중수소 방사능 모니터링에 관한 고찰)

  • SangJun Han;HongYeon Lee;BoGil Kim;HyeKyung Ha;YongJu Sin
    • Journal of Radiation Industry
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    • v.17 no.4
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    • pp.427-436
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    • 2023
  • As a result of evaluating the level of tritium emitted from the nuclear power plant in the environment and the human body, it was confirmed that tritium was detected in the environmental media and human urine samples to be investigated. It was found that the tritium was clearly detected. After the operation of the Tritium Removal Facility (TRF), which was operated for the purpose of removing tritium from the Wolsong nuclear power plant, the tritium emission showed a decreasing trend, and the tritium level in the environmental media also showed a tendency to decrease accordingly. However, for precise evaluation, it was necessary to select and investigate points by distance, season, and wind direction from the nuclear power plant, but it also showed characteristics that did not reflect this. As the cycle, etc., implemented the previous environmental monitoring program as it is, there was also a limitations in not being able to reflect the changing environment. Therefore, it is necessary to review and supplement the environmental monitoring investigation plan and results so far, and by applying the supplemented investigation plan to secure valid and reliable investigation results, it is judged that it will be an appropriate measure for environmental conservation and human protection in the vicinity of the nuclear power plant.

Tritium Fuel Cycle of the International Thermonuclear Experimental Reactor (국제핵융합실험로 삼중수소 연료주기)

  • Song, Kyu-Min;Sohn, Soon Hwan;Chung, Hongsuk;Yun, Sei-Hun;Jung, Ki Jung
    • Korean Chemical Engineering Research
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    • v.50 no.4
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    • pp.595-603
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    • 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.