• Title, Summary, Keyword: 삼중수소

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Tritium Concentrations of Tritiated Water Vapor and Tritiated Hydrogen in the Atmosphere in Taejon (대전지역 대기중 수증기상태 (HTO) 및 가스상태 (HT) 삼중수소의 농도)

  • Kim, C.K.;Han, M.J.;Kim, K.H.
    • Journal of Radiation Protection and Research
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    • v.22 no.2
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    • pp.97-101
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    • 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 $m^{-3}$.

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Hydrogen Brittleness on Welding Part for SDS Bottles (삼중수소 저장용기 이종 접합부의 수소 취성)

  • Kim, Raymund K.I.;Jung, Seok;Kang, Hyungoo;Chang, Minho;Yun, Seihun;Hong, Tae-Whan
    • Transactions of the Korean hydrogen and new energy society
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    • v.24 no.2
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    • pp.121-127
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    • 2013
  • Tritium was attracted with high energy source in neutron fusion energy systems. A number of research was performed in tritium storage materials. The Korea was raised storage and delivery systems (SDS) of international thermonuclear experimental reactor (ITER) research. However, bottles of SDS would be important because of stability. The bottles have a welding zone, this zone will be vulnerable to hydrogen embrittlement. This zone have a high thermodynamic energy and heat deterioration. Therefore bottles were studied about hydrogen embrittlement to retain stability. The heat treatment of hydrogen was carried under pressure-composition-temperature (PCT) apparatus because of checking at real time. And then, mechanical properties were evaluated by tensile test and hardness test. In results of this study, hydrogen atmosphere condition is very important by tensile test and kinetics test. The samples were evaluated, that is more weak hydrogen pressure, increasing temperature and time. This results could be useful in SDS bottle designs.

OVERVIEW OF HEALTH PHYSICS STUDIES ON TRITIUM BETA RADIATION (삼중수소 베타방사선에 관한 보건물리 연구의 적용)

  • Hwang, Sun-Tae;Hah, Suk-Ho
    • Progress in Medical Physics
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    • v.5 no.1
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    • pp.75-85
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    • 1994
  • As we enter the 2000s, there are four nuclear power units of the pressurized heavy water reactor-type in the commercial operation at the Wolsung Nuclear Power Plant(NPP) site where a larger amount of tritium ($\^$3/H) is released inevitably to the site environment. This radioctive nuclide is easily distributed throghout our environment because of its ubiquitous form as tritiated water (HTO) and its persistence in the environment. Tritum has certain characterisitics that present unique challenges for beta radiation dosimety and health risk assesment. In this paper, therefore, a variety of matters on tritium are considered and reviewed in terms of its characteristics and sources, metabolism and dosimetry, microdosimetry, radiobiology, risk assessment, and transport and cycling in the environment, etc.

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핵융합연료 삼중수소 분리반응탑 전산모사

  • 정흥석;이한수;안도희;황재영;김상환;손순환;정양근;송명재;일본명
    • Proceedings of the Korean Nuclear Society Conference
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    • pp.453-457
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    • 1996
  • 월성원자력발전소에서 생성되는 삼중수소는 핵융합로의 필수원료물질이다. 삼중수소 분리반응 탑에 소요되는 다단탑의 단수와 최적운전온도 및 반응탑의 효율을 결정하기 위하여, 흡수층과 촉매층으로 구성된 분리반응탑을 모델링하고, 전산코드를 작성하였다. 이 전산코드의 결과는 실험치와 잘 일치하였으며, 최소반응단수를 갖는 설계온도는 8$0^{\circ}C$임이 밝혀졌다.

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삼중수소 전처리과정이 방사능 측정결과에 미치는 영향평가

  • Lee, Byeong-Il;Jeong, Jin-Uk;Choe, Yeong-Hun
    • 대한방사선방어학회:학술대회논문집
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    • pp.82-83
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    • 2010
  • 환경시료 중 삼중수소의 방사능을 분석하기 위하여 전처리과정을 수행한다. 전처리의 주요 절차는 증류와 발광액의 첨가 그리고 약 24시간의 암실보관 등이다. 본 보고서에서는 각 전처리 과정이 방사능 측정결과에 미치는 영향을 평가하고 전처리과정에서 피할 수 없는 오차와의 관계를 확인한 후 이를 통해 삼중수소의 방사능 세기에 따라 전처리과정의 상대적 중요도를 확인하고자 한다. 이 과정을 통해 전처리가 꼭 필요한 경우와 그렇지 않은 경우를 구분할 수 있는 방사능 세기의 문턱 값을 확인하고자 한다.

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Comparison of Measured and Predicted $^3H$ Concentrations in Environmental Media around the Wolsung Site for the Validation of INDAC Code (주면피폭선량 평가코드(INDAC)의 검증을 위한 월성원전 주면 삼중수소 농도 실측치와 예측치의 비교 평가)

  • Jang, Si-Young;Kim, Chang-Kyu;Rho, Byung-Hwan
    • Journal of Radiation Protection and Research
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    • v.25 no.2
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    • pp.75-80
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    • 2000
  • The predicted results of INDAC code were compared with measured $^3H$ concentrations in air and pine-needle around the Wolsung site. The optimal sets of input data to INDAC were in addition selected by comparing the measured values with the predicted values of INDAC based on various conditions such as the release modes of effluents into the environment, the classification of wind classes, and the consideration of terrain. The predicted $^3H$ concentrations in air and pine-needle were shown to have good agreement with measured values, although there are some limitations such as uncertainties in measured values, complex topology around the site, and the land-sea breeze effects. The assumption on the $^3H$ behavior in vegetables or plants that the ratio of $^3H$ concentration in plant water to $^3H$ concentration in atmospheric water is 1/2 was shown to be conservative in terms of the audit calculation performed by the regulator. It was also found that data sets based on mixed mode and no terrain data were not appropriate for the audit calculation ensuring the compliance with regulations. Thus, if the mixed mode is considered as the release mode of effluents into the environment, meteorological data measured at 58 m height and terrain data should be used to evaluate the atmospheric dispersion factor.

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Prediction of the Tritium Behavior in Very High Temperature Gas Cooled Reactor Using TRITGO (TRITGO 코드를 이용한 초고온가스로 (VHTR) 삼중 수소 거동 예측)

  • Park, Jong-Hwa;Park, Ik-Kyu;Lee, Won-Jae
    • Journal of Radiation Protection and Research
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    • v.33 no.3
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    • pp.113-120
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    • 2008
  • In this study, The TRITGO code was introduced, which can predict the amount of tritium production, it's transport, removal, distribution and the level of contamination for the produced hydrogen by the tritium on the VHTR (very high temperature gas cooled reactor). The TRITGO code was improved so that the permeation to the IS Iodine Sulfide) loop for producing the hydrogen can be simulated. The contamination level of the produced hydrogen by the tritium was predicted by the improved code for the VHTR with 600MW thermal power. The contamination level for the produced hydrogen by tritium was predicted as 0.055 Bq/$H_2-g$. This level is three order of lower than the regulation value of 56 Bq/$H_2-g$ from Japan. From this study, the following results were obtained. it is important that the fuel coating (SiC layer) should be kept intact to prevent the tritium from releasing. Also it is necessary that the level of impurity such as 3He and Li in the helium coolant and the reflector consisting of the graphite should be kept as low as possible. It was found that the capacity of the purification system for filtering the impurities directly from the coolant will be the important design parameter.

삼중수소 내부피폭에 관한 연구

  • 박문수;곽성우;강창순
    • Proceedings of the Korean Nuclear Society Conference
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    • pp.913-917
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    • 1995
  • 인체내로 흡입된 삼중수소에 의한 영향을 평가하기 위한 기존의 내부피폭 평가 모델들을 검토하고, 이를 사용하여 body water와 OBT에 의한 선량을 계산하였다. 또한 이 모델들의 단점들을 도출하고, 이를 보안하기 위한 방안을 제시하였다.

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