• Title/Summary/Keyword: Nuclear Program

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Oleoylethanolamide Exhibits GPR119-Dependent Inhibition of Osteoclast Function and GPR119-Independent Promotion of Osteoclast Apoptosis

  • Kim, Hyun-Ju;Lee, Dong-Kyo;Jin, Xian;Che, Xiangguo;Choi, Je-Yong
    • Molecules and Cells
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    • v.43 no.4
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    • pp.340-349
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    • 2020
  • Oleoylethanolamide (OEA), a bioactive lipid in bone, is known as an endogenous ligand for G protein-coupled receptor 119 (GPR119). Here, we explored the effects of OEA on osteoclast differentiation, function, and survival. While OEA inhibits osteoclast resorptive function by disrupting actin cytoskeleton, it does not affect receptor activator of nuclear factor-κB ligand (RANKL)-induced osteoclast differentiation. OEA attenuates osteoclast spreading, blocks actin ring formation, and eventually impairs bone resorption. Mechanistically, OEA inhibits Rac activation in response to macrophage colony-stimulating factor (M-CSF), but not RANKL. Furthermore, the OEA-mediated cytoskeletal disorganization is abrogated by GPR119 knockdown using small hairpin RNA (shRNA), indicating that GPR119 is pivotal for osteoclast cytoskeletal organization. In addition, OEA induces apoptosis in both control and GPR119 shRNA-transduced osteoclasts, suggesting that GPR119 is not required for osteoclast apoptosis. Collectively, our findings reveal that OEA has inhibitory effects on osteoclast function and survival of mature osteoclasts via GPR119-dependent and GPR119-independent pathways, respectively.

Evaluation of Image Quality by Parameter Change in Onco Flash (Onco Flash에서 매개변수 변화에 따른 영상의 질 평가)

  • Cha, Eun-Sun;Noh, Ik-Sang;Kim, Ki;Choi, Choon-Ki;Seok, Jae-Dong
    • The Korean Journal of Nuclear Medicine Technology
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    • v.13 no.1
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    • pp.30-34
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    • 2009
  • Purpose: Many companies developed a lot of programs with continuous effort for program upgrading. With this acquire superior image quality for the purpose of quick examination and progress in spatial resolution. This study was to obtained clinical usefulness on a appropriate parameter of FWHM for speed and alpha value for superior image quality. Materials and Methods: Gamma camera by Siemens (e.cam) and spatial resolution phantom and four quadrant bar phantom used. Compared for FWHM by changed scan speed 15, 20, 25, 30, 35, 40 cm/min in scatter and non scatter in Onco Flash of spatial resolution phantom. Visual evaluation of count rate and bar phantom image for increased of alpha value of 10% in 0~100%. Results: FWHM by the scan speed was 9.37, 9.40, 9.28, 9.30, 9.31, 9.53 mm in the scatter. Count rate increased alpha value 10% increased. Visual evaluation was suitable to below 30%, Therefore spatial resolution improved on FWHM at the scan speed 25~35 cm/min applying for alpha value 30% in Onco Flash was average 9.3 mm less than FWHM of below 15 cm/min and above 40 cm/min. Conclusion: We found on appropriate parameter to progress of image quality. And there be a useful guideline for you that appropriate scan speed on vary in parameters of reduction on examination time and advancing image quality.

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Dosimetry and Medical Internal Radiation Dose of Re-188-DTPA for Endovascular Balloon Brachytherapy Against Restenosis after Coronary Angioplasty (혈관성형술 후 재협착 방지 치료에 사용하기 위한 원통형 풍선 Re-188-DTPA의 선량 분포와 내부피폭 선량)

  • Lee, Jin;Lee, Dong-Soo;Shin, Seung-Ae;Jeong, Jae-Min;Chung, June-Key;Lee, Myung-Chul
    • The Korean Journal of Nuclear Medicine
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    • v.33 no.2
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    • pp.163-171
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    • 1999
  • Purpose: Liquid beta emitter filled in angioplasty balloon could be used to perform endovascular balloon brachytherapy to prevent coronary artery restenosis. We investigated the dosimetry for Re-188-DTPA liquid-filled balloon and medical internal radiation dosimetry in case of balloon leakage. Materials and Methods: We estimated radiation dose from an angioplasty balloon (20 mm length, 3 mm diameter cylinder) to the adjacent vessel wall using Monte Carlo EGS4 code. We obtained time-activity curves of kidneys in normal dog and calculated $T_{max},\;T_{1/2}$. Using MIRDOSE3 program, we estimated absorbed doses to the major organs (kidneys, bladder) and the whole body when we assumed that balloon leaked all the isotope contained. Results: The radiation dose was 17.5 Gy at the balloon surface when we applied 3,700 MBq/ml of Re-188 for 100 seconds, Fifty percent of the energy deposited within 1 mm from the balloon surface. The estimated internal dose to the whole body was 0.005 mGy/MBq and 18.5 mGy for the spillage of 3,700 MBq of Re-188. Conclusion: We suggest that Re-188-DTPA can be used for endovascular balloon brachytherapy to inhibit coronary artery restenosis after angioplasty with tolerable whole body radiation dose in case of balloon rupture.

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Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle (선진 핵연료주기 기술 개발을 위한 핵연료주기 분석 기술)

  • Park, Byung-Heung;Ko, Won-Il
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.9 no.4
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    • pp.219-230
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    • 2011
  • The nuclear fuel cycle (NFC) analysis is a study to set a NFC policy and to promote systematic researches by analyzing technologies and deriving requirements at each stage of a fuel cycle. System analysis techniques are utilized for comparative analysis and assessment of options on a considered system. In case that NFC is taken into consideration various methods of the system analysis techniques could be applied depending on the range of an interest. This study presented NFC analysis strategies for the development of a domestic advanced NFC and analysis techniques applicable to different phases of the analysis. Strategically, NFC analysis necessitates the linkage with technology analyses, domestic and international interests, and a national energy program. In this respect, a trade-off study is readily applicable since it includes various aspects on NFC as metrics and then analyzes the considered NFC options according to the derived metrics. In this study, the trade-off study was identified as a method for NFC analysis with the derived strategies and it was expected to be used for development of an advanced NFC. A technology readiness level (TRL) method and NFC simulation codes could be utilized to obtain the required metrics and data for assessment in the trade-off study. The methodologies would guide a direction of technology development by comparing and assessing technological, economical, environmental, and other aspects on the alternatives. Consequently, they would contribute for systematic development and deployment of an appropriate advanced NFC.

The Optimal Energy Mix in South Korea's Electricity Sector for Low Carbon Energy Transition in 2030: In Consideration of INDC and Sequential Shutdown of Decrepit Nuclear Power Plants (저탄소 에너지 전환을 위한 2030년 최적전력구성비: 노후 원전 단계적 폐쇄와 INDC를 고려한 시나리오)

  • Kim, Dongyoon;Hwang, Minsup
    • Journal of Environmental Impact Assessment
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    • v.26 no.6
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    • pp.479-494
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    • 2017
  • After Fukushima incident, negative sentiment towards nuclear power has led to transition in policies that reduce the dependency on nuclear power in some countries. President Moon of Republic of Korea also announced a national plan of decommissioning retired nuclear power plants stage by stage. Therefore, nuclear power that once was considered the critical solution to energy security and climate change is now a limited option. This study aims to find an optimal energy mix in Korea's electricity system from 2016 through 2030 to combat climate change through energy transition with minimum cost. The study is divided into two different scenarios; energy transition and nuclear sustenance, to compare the total costs of the systems. Both scenarios show that electricity generated by wind technology increases from 2018 whereas that of photovoltaic(PV) increases from 2021. However, the total cost of the energy transition scenario was USD 4.7 billion more expensive than the nuclear sustenance scenario.

Image Quality of a Rotating Compton Camera Evaluated by Using 4-D Monte Carlo Simulation Technique (4-D 전산모사 기법을 이용한 호전형 컴프턴 카메라의 영상 특성 평가)

  • Seo, Hee;Lee, Se-Hyung;Park, Jin-Hyung;Kim, Chan-Hyeong;Park, Sung-Ho;Lee, Ju-Hahn;Lee, Chun-Sik;Lee, Jae-Sung
    • Journal of Radiation Protection and Research
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    • v.34 no.3
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    • pp.107-114
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    • 2009
  • A Compton camera, which is based on Compton kinematics, is a very promising gamma-ray imaging device in that it could overcome the limitations of the conventional gamma-ray imaging devices. In the present study, the image quality of a rotating Compton camera was evaluated by using 4-D Monte Carlo simulation technique and the applicability to nuclear industrial applications was examined. It was found that Compton images were significantly improved when the Compton camera rotates around a gamma-ray source. It was also found that the 3-D imaging capability of a Compton camera could enable us to accurately determine the 3-D location of radioactive contamination in a concrete wall for decommissioning purpose of nuclear facilities. The 4-D Monte Carlo simulation technique, which was applied to the Compton camera fields for the first time, could be also used to model the time-dependent geometry for various applications.

Contaminated Surfaces in an Urban Environment (도시환경에서 방사능오염 표면의 중요도 분석)

  • Hwang, Won-Tae;Jeong, Hyo-Joon;Kim, Eun-Han;Han, Moon-Hee;Ahn, Min-Ho;Kim, In-Kyu
    • Journal of Radiation Protection and Research
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    • v.36 no.3
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    • pp.148-153
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    • 2011
  • EMRAS-2 (Environmental Modelling for RAdiation Safety, Phase 2) is an international comparison program, which is organized by the International Atomic Energy Agency (IAEA), in order to harmonize the modelling of radionuclide behavior in the environment. To do so, the urban contamination working group within EMRAS-2 has designed the hypothetical scenarios for a specified urban area. In this study, the importance of contaminated surfaces composing an urban environment was analyzed in terms of dose rate using METRO-K, which has been developed to take a Korean urban environment into account. The contribution of contaminated surfaces to exposure dose rate showed distinctly a great difference as a function of specified locations and time following a hypothetical event. Moreover, it showed a distinct difference according to the existence of precipitation, and its intensity. Therefore, if an urban area is contaminated radioactively by any unexpected incidents such as an accident of nuclear power plants or an explosion of radioactive dispersion devices (RDDs), appropriate measures should be taken with consideration of the type of surface composing the contaminated environment in order to minimize not only radiation-induced health detriment but also economic and social impacts.

Power Generation Cost Comparison of Nuclear and Coal Power Plants in Year 2001 under Future Korean Environmental Regulations -Sensitivity and Uncertainty Analysis- (미래의 한국의 환경규제여건에 따른 2001년도의 원자력과 석탄화력 발전단가비교 -민감도와 불확실도 분석-)

  • Lee, Byong-Whi;Oh, Sung-Ho
    • Nuclear Engineering and Technology
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    • v.21 no.1
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    • pp.18-31
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    • 1989
  • To analyze the impact of air pollution control on electricity generation cost, a computer program was developed. POGEN calculates levelized discounted power generation cost including additional air pollution control cost for coal power plant. Pollution subprogram calculates total capital and variable costs using governing equations for flue gas control. The costs are used as additional input for levelized discounted power generation cost subprogram. Pollution output for Rue Gas Desulphurization direct cost was verified using published cost data of well experienced industrialized countries. The power generation costs for the year 2001 were estimated by POGEN for three different regulatory scenarios imposed on coal power plant, and by levelized discounted power generation cost subprogram for nuclear power. Because of uncertainty expected in input variables for future plants, sensitivity and uncertainty analysis were made to check the importance and uncertainty propagation of the input variables using Latin Hypercube Sampling and Multiple Least Square method. Most sensitive parameter for levelized discounted power generation cost is discount rate for both nuclear and coal. The control cost for flue gas alone reaches additional 9-11 mills/kWh with standard deviation less than 1.3 mills/kWh. This cost will be nearly 20% of power generation cost and 40% of one GW capacity coal power plant investment cost. With 90% confidence, the generation cost of nuclear power plant will be 32.6-51.9 mills/kWh, and for the coal power plant it will be 45.5-50.5 mills/kWh. Nuclear is favorable with 95% confidence under stringent future regulatory requirement in Korea.

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Comparative Evaluation of 18F-FDG Brain PET/CT AI Images Obtained Using Generative Adversarial Network (생성적 적대 신경망(Generative Adversarial Network)을 이용하여 획득한 18F-FDG Brain PET/CT 인공지능 영상의 비교평가)

  • Kim, Jong-Wan;Kim, Jung-Yul;Lim, Han-sang;Kim, Jae-sam
    • The Korean Journal of Nuclear Medicine Technology
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    • v.24 no.1
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    • pp.15-19
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    • 2020
  • Purpose Generative Adversarial Network(GAN) is one of deep learning technologies. This is a way to create a real fake image after learning the real image. In this study, after acquiring artificial intelligence images through GAN, We were compared and evaluated with real scan time images. We want to see if these technologies are potentially useful. Materials and Methods 30 patients who underwent 18F-FDG Brain PET/CT scanning at Severance Hospital, were acquired in 15-minute List mode and reconstructed into 1,2,3,4,5 and 15minute images, respectively. 25 out of 30 patients were used as learning images for learning of GAN and 5 patients used as verification images for confirming the learning model. The program was implemented using the Python and Tensorflow frameworks. After learning using the Pix2Pix model of GAN technology, this learning model generated artificial intelligence images. The artificial intelligence image generated in this way were evaluated as Mean Square Error(MSE), Peak Signal to Noise Ratio(PSNR), and Structural Similarity Index(SSIM) with real scan time image. Results The trained model was evaluated with the verification image. As a result, The 15-minute image created by the 5-minute image rather than 1-minute after the start of the scan showed a smaller MSE, and the PSNR and SSIM increased. Conclusion Through this study, it was confirmed that AI imaging technology is applicable. In the future, if these artificial intelligence imaging technologies are applied to nuclear medicine imaging, it will be possible to acquire images even with a short scan time, which can be expected to reduce artifacts caused by patient movement and increase the efficiency of the scanning room.

Large-scale 3D SSI Analysis using KIESSI-3D Program (KIESSI-3D 프로그램을 이용한 대형 3차원 SSI 해석)

  • Lee, Eun-Haeng;Kim, Jae-Min;Seo, Choon-Gyo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.26 no.6
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    • pp.439-445
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    • 2013
  • The soil-structure interaction(SSI) effect should be considered to accurately assess the seismic response of structure constructed on soft soil site other than the hard bedrock. Recently, the demand of SSI analysis has increased due to strengthening of the regulatory guidelines of nuclear power plant such as the USNRC SRP 3.7.2. In this study an accuracy and running time of the KIESSI-3D program for large-scale 3D SSI analysis were investigated. The seismic SSI analysis using the KIESSI-3D program was performed for several examples of large-scale three-dimensional soil-structure interaction system. The analysis results were compared with those of the ACS/SASSI program. Good agreements in transfer functions at selected locations showd that KIESSI-3D yields accurate solution for large-scale SSI problem. Moreover, it was found that running speed of the KIESSI-3D for large-scale 3D SSI analysis is much faster than that of the ACS/SASSI about 30~2000 times.