• Nuclear Engineering and Technology
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• 제45권2호
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• pp.203-210
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• 2013

The objective of this conducted research is to study the iodine removal efficiency in a self-priming venturi scrubber for submerged and non-submerged operating conditions experimentally and theoretically. The alkaline solution is used as an absorbent, which is prepared by dissolving sodium hydroxide (NaOH) and sodium thiosulphate ($Na2S_2O_3$) in water to remove the gaseous iodine ($I_2$) from the gas. Iodine removal efficiency is examined at various gas flow rates and inlet concentrations of iodine for submerged and non-submerged operating conditions. In the non-submerged venturi scrubber, only the droplets take part in iodine removal efficiency. However, in a submerged venturi scrubber condition, the iodine gas is absorbed from gas to droplets inside the venturi scrubber and from bubbles to surrounding liquid at the outlet of a venturi scrubber. Experimentally, it is observed that the iodine removal efficiency is greater in the submerged venturi scrubber as compare to a non-submerged venturi scrubber condition. The highest iodine removal efficiency of $0.99{\pm}0.001$ has been achieved in a submerged self-priming venturi scrubber condition. A mathematical correlation is used to predict the theoretical iodine removal efficiency in submerged and non-submerged conditions, and it is compared against the experimental results. The Wilkinson et al. correlation is used to predict the bubble diameter theoretically whereas the Nukiyama and Tanasawa correlation is used for droplet diameter. The mass transfer coefficient for the gas phase is calculated from the Steinberger and Treybal correlation. The calculated results for a submerged venturi scrubber agree well with experimental results but underpredicts in the case of the non-submerged venturi scrubber.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.169-179
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• 2023

Filtered containment system is a passive safety system that controls the over-pressurization of containment in case of a design-based accidents by venting high pressure gaseous mixture, consisting of air, steam and radioactive particulate and gases like iodine, via a scrubbing system. An indigenous lab scale facility was developed for research on iodine removal by venturi scrubber by simulating the accidental scenario. A mixture of 0.2 % sodium thiosulphate and 0.5 % sodium hydroxide, was used in scrubbing column. A modified mathematical model was presented for iodine removal in venturi scrubber. Improvement in model was made by addition of important parameters like jet penetration length, bubble rise velocity and gas holdup which were not considered previously. Experiments were performed by varying hydrodynamic parameters like liquid level height and gas flow rates to see their effect on removal efficiency of iodine. Gas holdup was also measured for various liquid level heights and gas flowrates. Removal efficiency increased with increase in liquid level height and gas flowrate up to an optimum point beyond that efficiency was decreased. Experimental results of removal efficiency were compared with the predicted results, and they were found to be in good agreement. Maximum removal efficiency of 99.8% was obtained.

• 상하수도학회지
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• 제28권5호
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• pp.549-554
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• 2014

This study was evaluated the applicability of the membrane filtration process (Micro Filtration (MF), nanofiltration membranes (NF), reverse osmosis (RO)) on the major radioactive substances, iodine ($I^-$) and cesium ($Cs^+$) using membranes produced in Korea and domestic raw water. Iodine ($I^-$) or cesium ($Cs^+$) in the microfiltration membrane (MF) process could not be expected removal efficiency by eliminating marginally at the combined state with colloidal and turbidity material. At the domestic raw water (lake water, turbidity 1.2 NTU, DOC 1.3 mg/L) conditions, nanofiltration membrane (NF) and reverse osmosis (RO) showed a high removal rate of about 88 ~ 99% for iodine ($I^-$) and cesium ($Cs^+$) and likely to be an alternative process for the removal of radioactive material.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3310-3316
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• 2022

Owing to the rising concerns about the safety of nuclear power plants (NPP), it is essential to study the venturi scrubber in detail, which is a key component of the filtered containment venting system (FCVS). FCVS alleviates the pressurein containment byfiltering and venting out the contaminated air. Themain objective of this research was to perform a CFD investigation of different configurations of a circular, non-submerged, self-priming venturi scrubber to estimate and improve the performance in the removal of elemental iodine from the air. For benchmarking, a mass transfer model which is based on two-film theory was selected and validated by experimental data where an alkaline solution was considered as the scrubbing solution. This mass transfer model was modified and implemented on a unique formation of two self-priming venturi scrubbers in series. Euler-Euler method was used for two-phase modeling and the realizable K-ε model was used for capturing the turbulence. The obtained results showed a remarkable improvement in the removal of radioactive iodine from the air using a series combination of venturi scrubbers. The removal efficiency was improved at every single data point.

• 한국환경보건학회지
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• 제24권2호
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• pp.20-31
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• 1998

There is a need for waste recycling. This study was carried out to investigate removal efficiency of TCE in water treatment with adsorbent made from coffee grounds which obtained after extraction of coffee through hot water. The removal of TCE in synthetic Waste water using adsorbents was examined varying dose, concentration and temperature on a laboratory scale. The results were as followed 1. As much as 95% TCE remogal was possible with adsorbent made from coffee grounds at an adsorbent dose over 2.5 g/l under the test conditions. 2. The removal rate of TCE was propotional to weight of adsorbent made from coffee grounds (0.025, 0.1, 0.3, 0.5 g). 3. In the effect of temperature, as temperature of wastewater was high, the rate of removal was increased. 4. Iodine number (865 mg/g) of adsorbent made from coffee grounds was not higher than that (1123 mg/g) of adsorbent made from coconut. But, in considering adsorption capacity, Iodine number was inapplicable to adsorbent made from coffee grounds. 5. Generally, Freundlich's equation applies to adsorption in wastewater. In case of TCE, slope (1/n) was 0.83, 1.06 and intercept (k) was 456.18, 405.19 at 150, 300 ppb respectively (average r=0.904, 0.933).

• Nuclear Engineering and Technology
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• 제52권5호
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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.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.463-469
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• 2003

2개의 보조건물(PAB와 SAB)이 있는 KSNP의 경우, 단일 보조건물만을 고려하고 있는 PWR-GALE 코드를 이용하여 기체배출량을 평가하기에는 한계가 있다. 본 논문에서는 기존 PWR-GALE 코드는 그대로 이용하면서 KSNP의 설계특성을 반영하기 위하여 일부 입력변수를 수정해서 보조건물 옥소방사능 배출량을 사실적으로 평가할 수 있는 방법론을 개발했다. 울진 5,6 호기의 설계자료를 이용하여 기존 평가방법론과 개선된 평가방법론을 적용해 사례연구를 실시하였다. 기존 평가방법으로 보조건물 옥소의 유효제거효율을 산출한 결과 42%가 나왔으나 PAB와 SAB의 옥소핵종 농도가 동일하다고 가정을 만족하지 못하는 단점이 있다. 개선된 평가방법으로 옥소의 유효제거효율을 산출한 결과 88%가 나왔다.

• Nuclear Engineering and Technology
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• 제53권5호
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• pp.1519-1523
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• 2021

Radioactive iodine (¹³¹I) released from nuclear power plants has been a critical environmental concern for workers. The effective trapping of radioactive iodine isotopes from the off-gas stream generated from nuclear facilities is an important issue in radioactive waste treatment systems evaluation. Numerous studies on retaining methyl iodide (CH₃I¹³¹) by impregnated activated carbons under the high content of moisture have been extensively studied so far. But there have been no good results on how to remove methyl iodide at high humid conditions up to now. A new challenge is to introduce other promising impregnating chemical agents that are able to uptake enough radioactive methyl iodide under high humid conditions. In order to develop a good removal efficiency to control radioiodine gas generated from a high humid process, activated carbons (ACs) impregnated with triethylene diamine (TEDA) and qinuclidine (QUID) were prepared. In addition, the removal efficiencies of the activated carbons (ACs) under humid conditions up to 95% RH were evaluated by applying the standard method specified in ASTM-D3808. Quinuclidine impregnated activated carbon showed a much higher decontamination factor above 1,000, which is enough to meet the regulation index for the iodine filters in nuclear power plants (NPPs).

• Nuclear Engineering and Technology
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• 제51권1호
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• pp.125-137
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• 2019

The purpose of this paper is to study the source term behavior after severe accidents by using a semi-kinetic model for simulation and calculation of in-containment activity. The reactor containment specification and the safety features of the containment under different accident conditions play a great role in evaluating the in-containment activity. Assuming in-vessel and instantaneous release of radioactivity into the containment, the behavior of in-containment isotopic activity is studied for noble gasses (Kr and Xe) and the more volatile elements of iodine, cesium, and aerosols such as Te, Rb and Sr as illustrative examples of source term release under LOCA conditions. The results of the activity removal mechanisms indicates that the impact of volumetric leakage rate for noble gasses is important during the accident, while the influence of deposition on the containment surfaces for cesium, mainly iodine isotopes and aerosol has the largest contribution in removal of activity during evolution of the accident.

• 대한환경공학회지
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• 제36권11호
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• pp.747-752
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• 2014

인공방사성핵종 I-131은 물속에서 요오드 이온($^{131}I^-$), 요오드산염 이온($^{131}IO_3{^-}$) 등 대부분 이온상태로 존재했으며 접촉시간이 짧을 경우, 정수약품(PACl)과 분말활성탄(PAC)에 의해 제거되지 않는 것으로 나타났다. 원수 탁도 증가에 따른 I-131의 제거 효과는 없었으나 분말활성탄과 I-131과의 접촉시간 증가에 따른 I-131의 제거율은 증가하는 것을 확인하였다. 혼합 주입(PACl + PAC)에 의한 I-131을 40% 이상 제거하기 위해서는 PACl 24 mg/L 이상, PAC 40 mg/L 이상을 주입해야 하는 것을 알 수 있었다. 모래여과에 의한 I-131은 제거되지 않은 것으로 나타났으며, 입상활성탄(GAC)에 의한 제거율은 신탄, 구탄 모두에서 최소검출한계 0.10 Bq/L 미만으로 거의 100% 제거됨을 알 수 있었다. 막에 의한 I-131의 제거율은 정밀여과막에 의해서는 제거되지 않았으며 역삼투막에서는 92%가 제거되었다.