• Title/Summary/Keyword: 삼중수소피폭

Search Result 32, Processing Time 0.017 seconds

벼의 성장시기에 따른 삼중수소 거동해석

  • 김상복;이원윤;박효국;임광묵;최용호;이창우
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1998.05b
    • /
    • pp.633-638
    • /
    • 1998
  • 벼의 성장시기에 다른 대기중 삼중수소의 식물채내 흡수실험을 수행하였다. 투명한 아크릴로 만들어진 피폭상자(50x60x120cm)내의 피폭조건은 비록 같은양(18.5 MBq)의 HTO를 증발시키더라도 동일한 농도를 유지하는 것이 거의 불가능하였다. 벼꽃의 매화 직후부터 수확기까지 이삭의 생성시기별로 HTO에 피폭시킨 후 잎, 줄기 및 이삭으로 구분된 시료에서 피폭 후 시간별로 조직자유수의 삼중수소 농토를 측정하였다. 조직자유수의 삼중수소 농도는 이삭에서 가장 느리게 감소하였으나 조직결합수의 삼중수소 농도는 이삭 성장이 가장 왕성한 시기에 높게 측정되었다.

  • PDF

Trends and Issues in Metabolism and Dosimetry for Tritium Intake (삼중수소 피폭방사선량 평가의 경향과 이슈에 대한 고찰)

  • Kim, Hee-Geun;Kong, Tae-Young;Jeong, Woo-Tae
    • Journal of Radiation Protection and Research
    • /
    • v.36 no.2
    • /
    • pp.99-106
    • /
    • 2011
  • Tritium is the one of the most important radionuclide for workers in nuclear power plants (NPPs) and the public, from the dosimetric point of view. Humans are likely to have internal radiation exposure by tritium inhalation. Radiation exposure by tritium accounts for approximately 7% and 60~90% of the total radiation exposure of NPP workers and the public during normal operation, respectively. Thus, many researches have been conducted to estimate the internal dose by tritium precisely in the world. In terms of tritium dosimetry, this paper provides the current status of research for tritium metabolism and dosimetry.

삼중수소 내부피폭에 관한 연구

  • 박문수;곽성우;강창순
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1995.05b
    • /
    • pp.913-917
    • /
    • 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.

  • PDF

월성원전의 삼중수소제거공정 최적화

  • 안도희;이한수;정홍석;송명재;손순환
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1995.05a
    • /
    • pp.824-828
    • /
    • 1995
  • 월성원전에서 삼중수소에 의한 작업자 피폭 및 환경방출량을 가능한 한 낮게 유지하기 위해서는 계통중수중에 축적되는 삼중수소를 근원적으로 제거할 수 있는 삼중수소제거시설이 필수적이다. 삼중수소제거공정은 방사선 안전성과 에너지 효율 측면에서 액상촉매교환과 초저온증류공정의 복합공정이 가장 효과적인 것으로 알려지고 있다. 본 연구에서는 월성원전의 후속기를 고려하여 용량이 연간 8MCi의 삼중수소제거시설에 대한 최적설계를 수행하였다. 액상촉매교환공정에 대해서는 NTU-HTU법 그리고 초전온증류공정에는 Fenske-Underwood-Gilliland법을 이용하여 공정을 해석하였고 공정내 삼중소소의 재고량이 최소가 되는 최적의 설계변수들을 제시하였다.

  • PDF

Evaluation Model and Experimental Validation of Tritium in Agricultural Plant (농작물의 삼중수소 오염평가 모델 개발 및 실험검증)

  • Kang Hee Suk;Keum Dong-kwon;Lee Hansoo;In Jun;Choi Yong Ho;Lee Chang Woo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.3 no.4
    • /
    • pp.319-328
    • /
    • 2005
  • This paper describes a compartment dynamic model for evaluating the contamination level of kritium in agricultural plants exposed by accidentally released tritium. The present model uses a time-dependent growth equation of plant so that it can predict the effect of growth stage of plant during the exposure time. The model including atmosphere, soil and plant compartments is described by a set of nonlinear ordinary differential equations, and is able to predict time-dependent concentrations of tritium in the compartments. To validate the model, a series of exposure experiments of HTO vapor on Chinese cabbage and radish was carried out at the different growth stage of each plant. At the end of exposure, the tissue free water(TFWT) and the organically bound tritium(OBT) were measured. The measured concentrations were agreed well with model predictions.

  • PDF

Analysis of Metabolism and Effective Half-life for Tritium Intake of Radiation Workers at Pressurized Heavy Water Reactor (중수로원전 종사자의 삼중수소 체내섭취에 따른 인체대사모델과 유효반감기 분석)

  • Kim, Hee-Geun;Kong, Tae-Young
    • 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.

Calculation of Internal Exposure Dose in Korean Man Resulting from Single and Chronic Intake of Tritium (트리튬($^{3}H$)의 단일(單一) 및 만성섭취(晩性攝取)에 대한 한국인(韓國人)의 내부피복(內部被曝) 선량(線量) 계산(計算))

  • Kim, Jang-Lyul;Yook, Chong-Chul;Ha, Chung-Woo
    • Journal of Radiation Protection and Research
    • /
    • v.8 no.2
    • /
    • pp.8-14
    • /
    • 1983
  • The doses to Korean adult by a single and chronic intake of tritiated water are determined using a three compartment model, which describes the retention of tritium radionuclide in body water and in bound organic form in the body. The results show that the total dose of a single intake, using retention half-time for the three-compartment of 9, 30, and 450 days, is 17.64 mrads ($176.4{\mu}Gy$) per 1mCi/kg ($3.7{\times}10^7Bq/kg$) intake, 97% of which is due to tritium in body water and 3% to bound tritium in tissue. In the chronic intake of 1mCi/day($3.7{\times}10^7Bq/day$) tritiated water, the total dose is 85.5 mrad/day(0.855mGy/day). Furthermore, in this study (MPC) a and (MPC)w values of tritium for Korean man are calculated by using the modified formula originated from ICRP Publication-2. From the results, we found that the (MPC) a, w values of ICRP underestimated approximately 50%, the (MPC)a, w values of Korean man must be elevated as high as approximately 50% than that of ICRP.

  • PDF

Comparison of the Regulatory Models Assessing Off-Site Radiological Dose due to the Routine Releases of Tritium (삼중수소의 환경방출에 따른 주민선량 규제모델의 비교)

  • Hwang Won-Tae;Kim Eun-Han;Han Moon-Hee;Choi Yong-Ho;Lee Han-Soo;Lee Chang-Woo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.3 no.2
    • /
    • pp.125-133
    • /
    • 2005
  • Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO) . A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEIIfTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment.

  • PDF