• Title/Summary/Keyword: Nuclear waste

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Revised Crackling Core Model Accounting for Fragmentation Effect and Variable Grain Conversion Time : Application to UO2 Sphere Oxidation (파편화 효과와 결정립 가변 전환시간을 고려한 Crackling Core Model의 개선 : UO2 구형 입자의 산화거동으로의 적용)

  • Lee, Ju Ho;Cho, Yung-Zun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.4
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    • pp.411-420
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    • 2018
  • This study presents a revised crackling core model for the description of $UO_2$ sphere oxidation in air atmosphere. For close reproduction of the sigmoid behavior exhibited in $UO_2$ to $U_3O_8$ conversion, the fragmentation effect contributing to the increased reactive surface area and the concept of variable grain conversion time were considered in the model development. Under the assumptions of two-step successive reaction of $UO_2{\rightarrow}U_3O_7{\rightarrow}U_3O_8$ and final grain conversion time equivalent to ten times the initial grain conversion time, the revised model showed good agreement with the experimental data measured at 599 - 674 K and a lowest deviation when compared with Nucleation and Growth model and AutoCatalytic Reaction model. The evaluated activation energy at 100% conversion to $U_3O_8$, $57.6kJ{\cdot}mol^{-1}$, was found to be closer to the experimentally extrapolated value than to the value determined in AutoCatalytic Reaction model, $48.6kJ{\cdot}mol^{-1}$.

A Preliminary Study on the Evaluation of Internal Exposure Effect by Radioactive Aerosol Generated During Decommissioning of NPPs by Using BiDAS (BiDAS를 적용한 원전 해체 공정 시 발생되는 방사성 에어로졸의 내부피폭 영향평가 사전 연구)

  • Song, Jong Soon;Lee, Hak Yun;Kim, Sun Il
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.4
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    • pp.473-478
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    • 2018
  • Radioactive aerosol generated in cutting and melting work during the NPP decommissioning process can cause internal exposure to body through workers' breath. Thus, it is necessary to assess worker internal exposure due to the radioactive aerosol during decommissioning. The actually measured value of the working environment is needed for accurate assessment of internal exposure, but if it is difficult to actually measure that value, the internal exposure dose can be estimated through recommended values such as the fraction of amount of intake and the size of particles suggested by the International Committee on Radiological Protection (ICRP). As for the selection of particle size, this study applied a value of $5{\mu}m$, which is the size of particles considering the worker recommended by the ICRP. As for the amount of generation, the amount of intake was estimated using data on the mass of aerosol generated in a melting facility at a site in Kozloduy, Bulgaria. In addition, using these data, this study calculated the level of radioactivity in the worker's body and stool and conducted an assessment of internal exposure using the BiDAS computer code. The internal exposure dose of Type M was 0.0341 mSv, that of Type S was 0.0909 mSv. The two types of absorption showed levels that were 0.17% and 0.45% of the domestic annual dose limit, respectively.

Effect of the Composition of a Reduced Fuel on the Concentration Change of UCl3 in the Electrorefiner (금속전환체 조성의 전해정련 전해조 UCl3 농도변화에 대한 영향)

  • Paek, Seungwoo;Lee, Chang-Hwa;Lee, Sung-Jai
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.3
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    • pp.347-353
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    • 2019
  • The composition of the reduced fuel produced in the electrolytic reduction process of pyroprocessing affects the concentration change of $UCl_3$, an important operating variable of the electrorefining process. In this study, we examined the concentration change of $UCl_3$ in the electrorefiner according to the content of TRU and RE elements in the reduced fuel and the concentration of $Li_2O$ introduced in the electrorefiner accompanied with the reduced fuel. Considering only the TRU and RE elements, the concentration of $UCl_3$ decreased with increasing the number of electrorefining operation batch. In order to operate one campaign (20 batches) of electrorefining process, it was found that additional injection of $UCl_3$ should be conducted more than 3 times. On the other hand, the concentration of $UCl_3$ in the electrorefiner changed significantly depending on the concentration of $Li_2O$ and, accordingly the number of operable electrorefining batches decreased rapidly, showing that the concentration of $Li_2O$ is an important operating variable in electrorefining. Therefore, the results of this study show that to maintain the concentration of $UCl_3$ in the electrorefiner, the operation mode should be set by taking into account the effect of $Li_2O$ as well as the TRU and RE elements contained in the reduced fuel.

Effects of Excavation Damaged Zone on Thermal Analysis of Multi-layer Geological Repository (다층 심지층처분장 열해석에 미치는 암반손상대의 영향)

  • Cho, Won-Jin;Kim, Jin-Seop;Kim, Geon Young
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.1
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    • pp.75-94
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    • 2019
  • As the present single-layer repository concept requires too large an area for the site of the repository, a multi-layer repository concept has been suggested to improve the disposal density. The effects of the excavation damaged zone around the multi-layer repository constructed in the deep host rock on the temperature distribution in the repository were analyzed. For the thermal analysis of the multi-layer repository, the hydrothermal model was used to consider the resaturation process occurring in the buffer, backfill and rock. The existence of an excavation damaged zone has a significant effect on the temperature distribution in the repository, and the maximum peak temperatures of double-layer and triple-layer repositories can rise to $7^{\circ}C$ and $12^{\circ}C$, respectively depending on the size of the excavation damaged zone and the degree of decrease of the thermal conductivity. The dominant factor affecting the peak temperature in the multi-layer repository is the decrease of thermal conductivity in the excavation damaged zone, and the excavation damaged zone formed around the deposition hole has more significant effects on the peak temperature than does the excavation damaged zone formed around the disposal tunnel.

Optimization for I-129 analytical method of radioactive waste sample using a high-temperature combustion tube furnace (고온연소로를 이용한 방사성 폐기물 내 I-129 정량 분석법 최적화 연구)

  • Chae-yeon, Lee;Jong-Myoung, Lim;Hyuncheol, Kim;Ji-Young, Park;Jin-Hong, Lee
    • Analytical Science and Technology
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    • v.35 no.6
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    • pp.256-266
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    • 2022
  • It is important to determine the concentration of long-lived radionuclides (e.g., 129I) in nuclear waste to ensure safety when handling it. To analyze nuclides in a solid sample (e.g., concrete and soil), it is essential to effectively separate and purify the nuclides of interest in the sample. This study reports the comprehensive efforts made to validate the analytical procedure for 129I detection in solid samples, using a high-temperature combustion furnace. 129I volatilized from the sample collected in 0.01 M HNO3 solution with a reducing agent (e.g., NaHSO3) and was rapidly measured by ICP-MS. Analytical conditions, such as pyrolysis temperature and types of mobile phase gas, catalyst, and trapping solution, were optimized to obtain a high recovery rate of spiked 129I. Finally, the optimized method was applied for the simultaneous analysis of other volatile radionuclides, such as 3H and 14C. The performance test results for the optimized method confirmed that the LSC (for 3H and 14C) and ICP-MS (for 129I) measurements, with the separation of volatile nuclides using a high-temperature combustion furnace, were reliable.

A Study on the Decontamination of Cs-137 and Sr-90 Contained in the Liquid Radioactive Waste Discharged from the Spent Fuel Storage Tank Using Microalgae (미세조류를 이용한 사용후핵연료 저장조에서 배출되는 방사성 폐액에 함유된 Cs-137 및 Sr-90 제염에 관한 연구)

  • Kim, Tae Young;Park, Hye Min;Song, Yang Soo;Lee, Un Jang
    • Resources Recycling
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    • v.31 no.5
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    • pp.20-25
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    • 2022
  • In this study, the applicability of microalgae was evaluated for eco-friendly decontamination of cesium-137 (Cs-137) and strontium-90 (Sr-90), which are radioactive nuclides contained in radioactive waste. The monolithic radioactive solution used in the experiment was manufactured at a concentration of 1.5 Bq/mL Cs-137 and 1.0 Bq/mL Sr-90 by diluting a standard radioactive solution and distilled water. This experiment used two types of microalgae, Chlorella Vulgaris was used for Sr-90 decontamination and Hematococcus pluvialis for Cs-137 decontamination. The experimental method is to put the microalgae cultured for 2 weeks into a bottle with a semi-permeable membrane, and then put the bottle in which the microalgae was put into the manufactured radioactive solution, so that the microalgae and the radioactive solution react through the semi-permeable membrane for 48 hours. For the radioactivity concentration analysis of each sample, a gamma-ray nuclide analyzer was used for Cs-137, a γ-ray isotope, and a Liquid Scintillation Count(LSC) was used f or Sr-90, a β-ray isotope. As a result of the experiment, it was confirmed that about 88.0 % of Cs-137 and about 89.7 % of Sr-90 could be decontaminated, and about 98.6 % of Sr-90 was finally able to be decontaminated by the two-stage decontamination method.

Preliminary Study on Candidate Host Rocks for Deep Geological Disposal of HLW Based on Deep Geological Characteristics (국내 심부 지질특성 연구를 통한 고준위방사성폐기물 심층처분 후보 암종 선행연구)

  • Dae-Sung Cheon;Kwangmin Jin;Joong Ho Synn;You Hong Kihm;Seokwon Jeon
    • Tunnel and Underground Space
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    • v.34 no.1
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    • pp.28-53
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    • 2024
  • In general, high-level radioactive waste (HLW) generated as a result of nuclear power generation should be disposed within the country. Determination of the disposal site and host rock for HLW deep geological repository is an important issue not only scientifically but also politically, economically, and socially. Considered host rock types worldwide for geological disposal include crystalline rocks, sedimentary rocks, volcanic rocks, and salt dome. However, South Korea consists of various rock types except salt dome. This paper not only analyzed the geological and rock mechanical characteristics on a nationwide scale with the preliminary results on various rock type studies for the disposal host rock, but also reviewed the characteristics and possibility of various rock types as a host rock through deep drilling surveys. Based on the nationwide screening for host rock types resulted from literature review, rock distributions, and detailed case studies, Jurassic granites and Cretaceous sedimentary rocks (Jinju and Jindong formations) were derived as a possible candidate host rock types for the geological disposal. However, since the analyzed data for candidate rock types from this study is not enough, it is suggested that the disposal rock type should be carefully determined from additional and detailed analysis on disposal depth, regional characteristics, multidisciplinary investigations, etc.

Review of In-situ Installation of Buffer and Backfill and Their Water Saturation Management for a Deep Geological Disposal System of Spent Nuclear Fuel (국외 사례를 통한 사용후핵연료 심층처분시스템 완충재 및 뒤채움재의 현장시공 및 포화도 관리 기술 분석)

  • Ju-Won Yun;Won-Jin Cho;Hyung-Mok Kim
    • Tunnel and Underground Space
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    • v.34 no.2
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    • pp.104-126
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    • 2024
  • Buffer and backfill play an essential role in isolating high-level radioactive waste and retard the migration of leaked radionuclides in deep geological disposal system. A bentonite mixture, which exhibits a swelling property, is considered for buffer and backfill materials, and excessive groundwater inflow from surrounding rock mass may affect stability and efficiency of their role as an engineered barrier. Therefore, stringent quality control as well as in-situ installation management and inflow water constrol for buffer and backfill are required to ensure the safety of deep disposal facilities. In this study, we analyzed the design requirements of buffer and backfill by examining various laboratory tests and a field study of the Steel Tunnel Test at the Äspö Hard Rock Laboratory in Sweden. We introduced how to control the quality of buffer and backfill construction in-field, and also presented how to handle excessive groundwater inflow into disposal caverns, validating the groundwater retention capacity of bentonite pellets and the effectiveness of geotexile use.

Uranium Recovery from Nuclear Fuel Powder Conversion Plant Filtrate and its Thermal Decomposition Characteristics (핵연료분말 제조공정에서 발생된 여액으로부터 우라늄 회수 및 회수된 우라늄 화합물의 열분해 특성)

  • Jeong, Kyung-Chai;Jeong, Ji-Young;Kim, Byung-Ho;Kim, Tae-Joon;Choi, Jong-Hyeun
    • Journal of the Korean Ceramic Society
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    • v.39 no.2
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    • pp.204-209
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    • 2002
  • In this study, $UO_4{\cdot}2NH_4F$, the precipitates which has low solubility, was obtained by chemical precipitation method to recover and reuse the trace uranium from the liquid waste producing in AUC process and for this compound it was characterized by means of chemical analysis, TG-DTA, XRD and FT-IR analyses. This compound was analyzed as $UO_4{\cdot}2NH_4F$ and shape of this precipitate was hexagonal type, having the size of 2∼3 ${\mu}m$. Also, the intermediates were obtained as $UO_4F,\;UO_4,\;UO_3,\;and\;U_3O_8$ by the thermal decomposition over the temperature of 220, 310, 515 and 640$^{\circ}C$, respectively. It is concluded that under the condition of a constant heating rate of 5$^{\circ}C$/min in air atmosphere range of between room temperature and 800$^{\circ}C$, thermal decomposition reaction mechanism of $UO_4{\cdot}2NH_4F$ is as follow; $UO_4{\cdot}2NH_4F{\rightarrow}UO_4F{\rightarrow}UO_4{\rightarrow}UO_3{\rightarrow}U_3O_8$.

The Perception of Middle School Teachers about the Environmental Problem (환경문제에 대한 중학교 교사들의 인식)

  • Park, Jaemoon;Lee, Sujin;Moon, Seongbae
    • Journal of the Korean Chemical Society
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    • v.58 no.6
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    • pp.590-599
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    • 2014
  • Environmental education, effectively performed at school, is very important to solve the environmental problems. Moreover the survey for teacher's perception is essential. The purpose of the study was to investigate the perception of environmental problems of middle school teachers in Pusan. The survey was done twice in 2007 and 2012, and based on the time intervals, careers, and major of the teachers. 200 teachers were chosen in 2007 and 300 teachers in 2012. How many environmental problems occurred during this time period affected the 471 teachers' perception was investigated and analyzed. The results are as follows. First, the perception difference of environmental problems was meaningful between two time intervals (p<.01). Especially, the perception of modern environmental problems and carbon emission showed considerable increase in both science and non-science major teachers. This may be caused by the climate change and the severity of lifestyles of indiscriminate consumerism. Second, the perception difference of environmental problems by careers was also meaningful (p<.01). Overall, the perception was obvious on the aspects of modern environmental problems, carbon emission, destruction of ozone layers, nuclear wastes, environmental hormones, and red tides. Teachers, having more careers irrespective of their teaching subjects, showed higher perception on the seriousness of environmental pollution, the necessity of environmental conservation, and the importance of health. Third, the perception of environmental problems between science and non-science major teachers was meaningful (p<.01). Particularly, the perception in the broad environmental problems was distinctive between them.