• Title/Summary/Keyword: Classification of radioactive waste

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Study on Q-value prediction ahead of tunnel excavation face using recurrent neural network (순환인공신경망을 활용한 터널굴착면 전방 Q값 예측에 관한 연구)

  • Hong, Chang-Ho;Kim, Jin;Ryu, Hee-Hwan;Cho, Gye-Chun
    • Journal of Korean Tunnelling and Underground Space Association
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    • v.22 no.3
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    • pp.239-248
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    • 2020
  • Exact rock classification helps suitable support patterns to be installed. Face mapping is usually conducted to classify the rock mass using RMR (Rock Mass Ration) or Q values. There have been several attempts to predict the grade of rock mass using mechanical data of jumbo drills or probe drills and photographs of excavation surfaces by using deep learning. However, they took long time, or had a limitation that it is impossible to grasp the rock grade in ahead of the tunnel surface. In this study, a method to predict the Q value ahead of excavation surface is developed using recurrent neural network (RNN) technique and it is compared with the Q values from face mapping for verification. Among Q values from over 4,600 tunnel faces, 70% of data was used for learning, and the rests were used for verification. Repeated learnings were performed in different number of learning and number of previous excavation surfaces utilized for learning. The coincidence between the predicted and actual Q values was compared with the root mean square error (RMSE). RMSE value from 600 times repeated learning with 2 prior excavation faces gives a lowest values. The results from this study can vary with the input data sets, the results can help to understand how the past ground conditions affect the future ground conditions and to predict the Q value ahead of the tunnel excavation face.

A Numerical Analysis to Estimate Disposal Spacing and Rock Mass Condition for High Efficiency Repository Based on Temperature Criteria of Bentonite Buffer (벤토나이트 완충재 설계 기준 온도에 따른 고효율 처분시스템 처분 간격 및 암반 조건 산정을 위한 수치해석적 연구)

  • Kim, Kwang-Il;Lee, Changsoo;Kim, Jin-Seop;Cho, Dongkeun
    • Tunnel and Underground Space
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    • v.31 no.4
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    • pp.289-308
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    • 2021
  • This study conducts coupled thermo-hydro-mechanical numerical modeling to investigate the maximum temperature and conditions for securing mechanical stability of the high-level radioactive waste repository when temperature criteria of bentonite buffer are 100℃ and 125℃, respectively. In case of temperature criterion of buffer as 100℃, the maximum temperatures at the interface between canister and buffer are calculated to be 99.4℃ and 99.8℃, respectively for a case with disposal tunnel spacing of 40 m and deposition hole spacing of 5.5 m and for the other case with disposal tunnel spacing of 30 m and deposition hole spacing of 6.5 m. In case of temperature criterion of buffer as 125℃, spacings of disposal tunnel and deposition hole could be decreased to 30 m and 4.5 m, respectively, which reduces the disposal area up to 55% compared to the disposal area of KRS+. According to analysis of mechanical stability for various disposal spacings, RMR of rock mass for KRS+ should be larger than 72.4 which belongs to good rock in RMR classification to prevent failure of rock mass. As disposal spacing is decreased, required RMR of rock mass is increased. In order to prevent failure of rock mass for a case with disposal tunnel spacing of 30 m and deposition hole spacing of 4.5 m, RMR larger than 87.3 is needed. However, mechanical stability of the repository is secured for all cases with RMR over 75 considering the enhancement of rock strength due to confining stress induced by swelling of the bentonite buffer and backfill.

Preliminary Result of Lineament Analysis for the Potential Site Selection of HLW Geological Disposal (HLW 지층처분 광역 후보부지 선정을 위한 선형구조 예비 분석 결과)

  • Ko, Kyoungtae;Kihm, You Hong;Lee, Hong-Jin
    • Economic and Environmental Geology
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    • v.51 no.2
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    • pp.167-176
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    • 2018
  • It is necessary to consider various geological parameters such as lithology, geological structure, earthquake, hydraulic geology, geochemistry, geological engineering, and geothermal in order to select potential sites for HLW(high-level radioactive waste) geological disposal. In particular, the geological lineament reflects the characteristics of various geological parameters and can be used as an important criterion for site selecting such as nuclear power plants and HLW repositories. In this paper, the Finnish lineament classification method for HLW disposal site selection through the lineament analysis was applied to the lineament data in the Korean peninsula. For this purpose, we used previous lineament data from the KIGAM(Korea Institute of Geoscience and Mineral Resources) and obtained new lineament data from the field geologists such as structural geologist, paleoseismologist, and geomorphologist. To ensure the reliability of the new lineament analysis data, we used high-resolution satellite images and hill-shade relief maps which were constructed by a digital elevation model. In the prevailing direction analysis from the acquired lineament data, the NNE-SSW direction was the most dominant, but the ENE-WSW and NNW-SSE directions also showed highly frequency depending on the experts. Applying the Finnish classification method, the geometrical development characteristics of the lineament corresponding to the Class 1 and 2 used for the wide-wide candidate site were compared. As a result of direction analysis for Class 1, the NNE-SSW direction was the most dominant and the WNW-ESE direction also showed a high frequency. In the case of Class 2, the NNE-SSW is the most prevalent and WNW-ESE or ENE-WSW direction also had highly frequency depending on the experts. Different lineament analysis results based on the same data are interpreted as a result of subjective experience and analytical criteria from the every experts. Therefore, it is necessary to establish integrated criteria and consider geophysical data for the publication of reliable nation-wide lineament map.

Trends of Study and Classification of Literatures on Environmental Pollution in Korea (우리나라에서의 환경오염 관련 문헌분류 및 연구동향)

  • 배준형;이종영;장봉기
    • Journal of Environmental Health Sciences
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    • v.22 no.3
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    • pp.37-48
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    • 1996
  • The purpose of this study is to provide the valuable basic information that helps set the advanced direction of study in environmental pollution in the future. It classifies and analyzes 6, 531 papers according to their years, fields, and contents from 1962 to 1993 in Korea through Chunrian, a PC communication network, National Environment Research Institute(1989) in Seoul. Classifying papers by their fields, this study shows 19.6%(1, 281 papers) of total papers on water pollution, on which most emphasis was placed in the studies, 17.2%(1, 121 papers) on general remarks, 14.6%(952 papers) on environmental ecology, and 13.6%(891 papers) on air pollution. Classifying papers by their contents, this study tells us that the survey of state and evaluation of pollution degree took 28%(1, 829 papers) of total papers, and it seemed the most active study was carried out on this content. It then shows us that the treatment technology and mechanism shared 17.5%(1, 144 papers), and facilities and design took 1.9%(127 papers) which needed more studies in the future. As for the trends of study, the papers published until 1979 show that the water pollution accounted for 28.9% of total studies, on which the greatest emphasis was placed, while the papers in 1990s tell us that general remarks 34.7%, air pollution 14.9%, and water pollution 14.1%. It also shows that treatment technology and mechanism has had more importance since 1980s in water pollution, noise and vibration, waste materials, human wastes, and radioactive pollution. However, in sea pollution, policy and standard rather than treatment technology or method of measurement and analysis has been considered a more important one in 1990s. Analyzing the studies on general remarks, it tell us that the paper on environmental act, which were frequently conducted, accounted for 33.3% until 1979, while the papers on the environmental policy, in which the highest interest was kept, accounted 34.6% in 1990s. This study concludes that most papers had examined the survey on status and evaluation of pollution degree before 1980, while studies on solving the problems of environmental pollution have had more importance in the 1980s and 1990s. Therefore, in the future, more studies should be conducted actively on policy development to solve the problems of environment pollution as well as on encouragement of environmental consciousness.

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A Comparative Study on Effective One-Group Cross-Sections of ORIGEN and FISPACT to Calculate Nuclide Inventory for Decommissioning Nuclear Power Plant

  • Cha, Gilyong;Kim, Soonyoung;Lee, Minhye;Kim, Minchul;Kim, Hyunmin
    • Journal of Radiation Protection and Research
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    • v.47 no.2
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    • pp.99-106
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    • 2022
  • Background: The radionuclide inventory calculation codes such as ORIGEN and FISPACT collapse neutron reaction libraries with energy spectra and generate an effective one-group cross-section. Since the nuclear cross-section data, energy group (g) structure, and other input details used by the two codes are different, there may be differences in each code's activation inventory calculation results. In this study, the calculation results of neutron-induced activation inventory using ORIGEN and FISPACT were compared and analyzed regarding radioactive waste classification and worker exposure during nuclear decommissioning. Materials and Methods: Two neutron spectra were used to obtain the comparison results: Watt fission spectrum and thermalized energy spectrum. The effective one-group cross-sections were generated for each type of energy group structure provided in ORIGEN and FISPACT. Then, the effective one-group cross-sections were analyzed by focusing on 59Ni, 63Ni, 94Nb, 60Co, 152Eu, and 154Eu, which are the main radionuclides of stainless steel, carbon steel, zircalloy, and concrete for decommissioning nuclear power plant (NPP). Results and Discussion: As a result of the analysis, 154Eu and 59Ni may be overestimated or underestimated depending on the code selection by up to 30%, because the cross-section library used for each code is different. When ORIGEN-44g, -49g, and -238g structures are selected, the differences of the calculation results of effective one-group cross-section according to group structure selection were less than 1% for the six nuclides applied in this study, and when FISPACT-69g, -172g, and -315g were applied, the difference was less than 1%, too. Conclusion: ORIGEN and FISPACT codes can be applied to activation calculations with their own built-in energy group structures for decommissioning NPP. Since the differences in calculation results may occur depending on the selection of codes and energy group structures, it is appropriate to properly select the energy group structure according to the accuracy required in the calculation and the characteristics of the problem.