• Title/Summary/Keyword: Radioactive gas

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Capture of Volatile Organic Iodine Species Using Mordenites

  • Tejaswini Vaidya;John P. Stanford;Nicolene van Rooyen;Krishnan Raja;Vivek Utgikar;Piyush Sabharwall
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.21 no.2
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    • pp.205-224
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    • 2023
  • The emission of off-gas streams from used fuel recycling is a concern in nuclear energy usage as they contain radioactive compounds, such as, 3H, 14C, 85Kr, 131I, and 129I that can be harmful to human health and environment. Radioactive iodine, 129I, is particularly troublesome as it has a half-life of more than 15 million years and is prone to accumulate in human thyroid glands. Organic iodides are hazardous even at very low concentrations, and hence the capture of 129I is extremely important. Dynamic adsorption experiments were conducted to determine the efficiency of sodium mordenite, partially exchanged silver mordenite, and fully exchanged silver mordenite for the removal of methyl iodide present at parts per billion concentrations in a simulated off-gas stream. Kinetic analysis of the system was conducted incorporating the effects of diffusion and mass transfer. The possible reaction mechanism is postulated and the order of the reaction and the values of the rate constants were determined from the experimental data. Adsorbent characterization is performed to investigate the nature of the adsorbent before and after iodine loading. This paper will offer a comprehensive understanding of the methyl iodide behavior when in contact with the mordenites.

Numerical Modelling for the Dilation Flow of Gas in a Bentonite Buffer Material: DECOVALEX-2019 Task A (벤토나이트 완충재에서의 기체 팽창 흐름 수치 모델링: DECOVALEX-2019 Task A)

  • Lee, Jaewon;Lee, Changsoo;Kim, Geon Young
    • Tunnel and Underground Space
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    • v.30 no.4
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    • pp.382-393
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    • 2020
  • The engineered barrier system of high-level radioactive waste disposal must maintain its performance in the long term, because it must play a role in slowing the rate of leakage to the surrounding rock mass even if a radionuclide leak occurs from the canister. In particular, it is very important to clarify gas dilation flow phenomenon clearly, that occurs only in a medium containing a large amount of clay material such as a bentonite buffer, which can affect the long-term performance of the bentonite buffer. Accordingly, DECOVALEX-2019 Task A was conducted to identify the hydraulic-mechanical mechanism for the dilation flow, and to develop and verify a new numerical analysis technique for quantitative evaluation of gas migration phenomena. In this study, based on the conventional two-phase flow and mechanical behavior with effective stresses in the porous medium, the hydraulic-mechanical model was developed considering the concept of damage to simulate the formation of micro-cracks and expansion of the medium and the corresponding change in the hydraulic properties. Model verification and validation were conducted through comparison with the results of 1D and 3D gas injection tests. As a result of the numerical analysis, it was possible to model the sudden increase in pore water pressure, stress, gas inflow and outflow rate due to the dilation flow induced by gas pressure, however, the influence of the hydraulic-mechanical interaction was underestimated. Nevertheless, this study can provide a preliminary model for the dilation flow and a basis for developing an advanced model. It is believed that it can be used not only for analyzing data from laboratory and field tests, but also for long-term performance evaluation of the high-level radioactive waste disposal system.

Air Content and Fluidity Properties of Cement Matrix according to Anthracite Particle-size (안트라사이트 입도에 따른 시멘트 경화체의 공기량 및 유동성 특성)

  • Kyoung, In-Soo;Pyeon, Su-Jeong;Lee, Sang-Soo
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2017.11a
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    • pp.92-93
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    • 2017
  • Recently, there has been an increasing interest in natural radioactive gas radon(Rn-222), the problem of indoor air quality pollution to worldwide. It has been scientifically proven to be hazardous to various diseases such as lung cancer and skin cancer if the human body is exposed to long-term accumulation of atomic nuclei due to the destruction of radon and alpha lines. Based on the indoor air quality control policy, this study is a basic experiment in the manufacture of a selective elimination function to containing radon adsorption and reduction of radon concentration, which is used to absorb radioactive isotopes such as phosphorus and radon in indoor environment.

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Hydrophobic Catalyst Mixture for the Isotopic Exchange Reaction between Hydrogen and Water

  • Paek S.;Ahn D.H.;Choi H.J.;Kim K.R.;LEE M.;YIM S.P.;CHUNG H.
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11b
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    • pp.141-148
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    • 2005
  • Pt/SDBC catalyst, which is used for the hydrogen-water isotopic exchange reaction, was prepared. The various properties of the catalyst, such as the thermal stability, pore structure and the platinum dispersion, were investigated. A hydrophobic Pt/SDBC catalyst which has been developed for the LPCE column of the WTRF (Wolsong Tritium Removal Facility) was tested in a trickle bed reactor. An experimental apparatus was built for the test of the catalyst at various temperatures and gas velocities.

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A Study on Harmful Radioactive Gas(Rn$_222$)-Concentration in Soils, Taejeon City (대전지역 토양에서 유해 방사성가스인 라돈 농집에 대한 연구)

  • 김승오;김해경
    • Journal of Environmental Science International
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    • v.6 no.5
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    • pp.489-496
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    • 1997
  • The arm of this study is to determine harmful radioactive gas($Rn^{222}$)-concentrations in soils and to suggest the anormalous regions of $Rn^{222}$-concentration in Taejeon area. The range of $Rn^{222}$-concentration in the soils (45 samples) of the survey area is 100 to 2, 475 (pCi/L) and mean$\pm$$\sigma$ of those values is 489$\pm$ 505 (pCi/L). The 2% (4 samples) of soil-gas samples (45 ones) collected In the survey area is corresponded to high rusk level, 53% (24 samples) to medium one and 43% (19 samples) to low one. Especially. The $Rn^{222}$-concentration is relatively higher in schistose granite region than in other rock Mts (two-mica granite and biotite ganite) in the survey area. The $Rn^{222}$-concentration is propotional to the uranium contents in the soils. The soil hardness among the various factors is correlative with $Rn^{222}$-concentrations. To prevent the damage from $Rn^{222}$-concentrations, It is necessary to close the cracks of underground structure and to consider methods reducing $Rn^{222}$-concentration for the anormalous regions.

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A Preliminary Study on Soil-Gas 222Rn Concentrations Depending on Different Bedrock Geology (기반암에 따른 토양가스 222Rn농도의 분포에 관한 기초연구)

  • Je, Hyun-Kuk;Kang, Chigu;Chon, Hyo-Taek
    • Economic and Environmental Geology
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    • v.31 no.5
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    • pp.415-424
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    • 1998
  • In order to investigate soil-gas $^{222}Rn$ concentrations, Kwanak Campus (Seoul National University), Boeun (Choong-buk) and Gapyung (Kyonggi) areas were selected and classified depending on their base rock types. Radon risk indices of these study areas decrease in the order of Gapyung>Kwanak Campus>Boeun areas, and in the order of rock type as banded gneiss>granite gneiss>granite>black slate-shale>mica schist>shale-lirnestone>phyllite-schist. Radon emanating trends with water content and grain size of soils were assessed by modified Morse 3 min. method. Radon emanation increases with the increase of water content in soils which is lower than 6~16 wt.%, and decreases in the range of higher than 6-16 wt. %. It shows that Rn emanation increases with the decrease of soil grain size. Radioactivity analysis of radionuclides of 238U series in some soil samples shows that radioactive disequilibrium state between $^{226}Ra$ and $^{238}U$ exists owing to different geochemical behavior of each radionuclide, and, it is necessary to carry out radioactive isotope geochemical approach for soil-gas $^{222}Rn$ study.

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A Status of Tritium Processing Technologies (트리튬 처리기술 현황)

  • 안도희;김광락;백승우;이민수;임성팔;정흥석
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.172-179
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    • 2003
  • Various type of tritium wastes can be produced from nuclear fuel cycle process satisfying non-proliferation, CANDU reactors, and nuclear industry. Activities of tritium processing in the world were surveyed to develope the processing technologies of tritium wastes. The tritium wastes were classified into gas phase, liquid phase, and organic phase. And the treatment techniques for the tritium wastes are analyzed. Development of tritium processing technologies is essential to finding public acceptance of radioactive wastes and forming a solid foundation to foster the growth of nuclear industry in Korea.

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Removal of radioactive methyliodide from the gas stream with a composite sorbent based on polyurethane foam

  • Obruchikov, Alexander V.;Magomedbekov, Eldar P.;Merkushkin, Aleksei O.
    • Nuclear Engineering and Technology
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    • v.52 no.5
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    • pp.1093-1097
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    • 2020
  • A composite iodine sorbent was obtained in the form of porous polymer matrix with activated carbon particles impregnated with triethylenediamine deposited on its surface. A comparative assessment of the radioactive methyliodide capturing efficiency by the composite sorbent and a sample of industrial charcoal sorbent was conducted. It was shown that under the selected testing conditions, the hydraulic resistance of the composite sorbent is lower, and the sorption capacity is higher than that of the industrial charcoal sorbent. A method for comparing the effectiveness of iodine sorbents, based on the calculation of the ratio of the sorption capacity index to the minimum capacity index, needed for the required purification degree was proposed.

The Removal of Carbon-14 Scrubber for Removal of Environmental Radioactive Carbon in a Heavy Water Reactor (중수로 환경방출 방사성이산화탄소 제거 장치 개발)

  • 강덕원;지준화;엄희문
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.509-513
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    • 2003
  • The radioactive Carbon, C-14, although present in small amount, emits a high energy(up to 0.156MeV) $\beta$ ray and has extremely long half-life(5730years). So special monitoring and management on its generation and discharge is inevitable. A PHWR, due to its own specific designs generates about six times as much C-14 as a PWR does and over 90% of the discharged C-14 comes from the Moderator system and discharged in to the environment through the process of periodic purging of the moderator cover gas system. The present study focussed on the development of effective C-14 scrubber and after production of a test facility and experiments using it, we found that our test facility is very efficient in $CO_2$ removal.

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