• Title/Summary/Keyword: 삼중해

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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.