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엔지오텐신이 Norepinephrine의 신혈관 반응에 미치는 영향
이석호,김종규,양훈모,민영기,임한혁 순천향의학연구소 1999 Journal of Soonchunhyang Medical Science Vol.5 No.2
To determine the effect of angiotensin Ⅱ(ANG Ⅱ)-induced hypertension on the renal hemodynamic response of norepinephrine(NE), mongrel dog instrumented for checking of renal blood flow(RBF) was followed as the step increases every 2 minutes in the rate of norepinephrine infusion into the renal artery during 5 conditions (C : control, C+PD : control+pressure decompression of aorta, ACEI : angiotensin converting enzyme inhibitor, ACEI+ANG Ⅱ : angiotensin converting enzyme inhibitor+ANG Ⅱ, ACEI+ANG Ⅱ+PD : angiotensin converting enzyme inhibitor+ANG Ⅱ+pressure decompression of aorta) Without relation of increase (C, C+PD) or decrease (ACEI+ANG Ⅱ, ACEI+ANG Ⅱ+PD) of the plasma ANG Ⅱ level when NE is infused into vessel, there were no differences in RBF response to NE infusion between C and C+PD and between ACEI+ANG Ⅱ and ACEI+ANG Ⅱ+PD, which implies that renal arterial pressure(RAP) does not play an important role in controling the renal hemodynamic response to NE. When renin angiotensin system was blocked by captopril without adding to ANG Ⅱ supply (ACEI), RBF can be severe decreased to approximately 90% at much lower rates of NE infusion than occurred when the sufficient concentration of ANG Ⅱ were present in the plasma. As the increased sensitivity of NE did not occur at lower renal arterial pressure, when ANGⅡ was present in the plasma in sufficient concentrations, it seems that protective effect on renal function is possible by ANGⅡ during renal sympathetic stimulation.
A study of Migration FEP in the high-Level RadWaste disposal environment
Hun Suk Im,Seonggyu Choi,Jang-Soon Kwon 대한지질학회 2021 대한지질학회 학술대회 Vol.2021 No.10
The safety of the high-level radioactive waste disposal system is evaluated for how and how much radioactive materials leaked from the disposal site through engineering and natural barriers to the ecosystem. The possible path or the scenario of a radionuclide migration is based on FEP: Features means unique element being likely to occur in the disposal system, Events is natural or anthropological case affecting the performance and safety of disposal system in a relatively short period of time and Process is a natural or artificial process having the potential to affect the disposal system"s performance and safety. The utilization of FEPs has so far focused on the safety assessment of disposal systems after being selected according to its significance from an expert point of view. However, as FEPs contain organic information with system evolution and radionuclide migration, which can extend its utilization into the analysis of radionuclide behavior in a high-level radioactive waste disposal environment. Therefore, this study analyzed the system evolution FEPs and migration FEPs for POSIVA in Finland with geological/mineralogical similarities to Korea. Migration FEPs were rearranged based on the relation with system evolution FEPs and the several factors were also summarized to understand migration behaviors, which will be used as important strategic map for engineering and field-scale experiments forward.
Strategic Study on Various Optional Treatment Processes for Disposal of Spent Nuclear Fuel
Hun-Suk Im,Hong Jang,Hyo-On Nam,Won-Il Ko,Yong Zun Cho 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.2
As an alternative technology for the efficient disposal of spent nuclear fuel, various process flows can be selected based on the recovered and separated radioactive nuclide group. This is to examine the efficiency of the disposal area of spent nuclear fuel when various disposal technologies and several treatment processes are applied to spent nuclear fuel, compared to the deep geological disposal of burying the entire spent fuel in the ground. Above all, the biggest advantage of the optional treatment processes is that it can be applied to various disposal methods (deep borehole disposal, deep geological disposal) because it can process spent fuel in various sizes and separate into some groups according to the properties of radionuclides. These optional processes are not new technology and currently available as of today, and the level is classified based on the stepwise separation of high heat emission nuclides and long half-life nuclides. This is to increase the efficiency of the disposal of spent nuclear fuel by separating and managing high-risk radionuclides separately. Relatively various optional processes are possible depending on the level, and characteristic analysis is performed on wastes treated with alternative technologies. The mass balance for each option process is completed, and the amount of waste is also calculated accordingly. These are used as basic data for waste disposal area and economic evaluation. Besides it is easy to process spent fuel of various sizes suitable for deep geological disposal or deep borehole disposal technology when an optional treatment technology is applied to spent fuel. However, since this selective process is based on the process structure constructed in a broad framework, it is considered that additional follow-up studies are needed not only on detailed technology but also on the flow and amount of waste.
Option Strategies on the Pre-management Processes of Spent Nuclear Fuel for Waste Disposal System
Hun Suk Im,Hong Jang,Hyo On Nam,Won Il Ko,Yong-Zun Cho 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.1
Korea Atomic Energy Research Institute (KAERI) has investigated Pyroprocessing technology in order to decrease the burden of disposal system and increase availability of useful radionuclides in the spent nuclear fuel (SNF) for future. The treatment and the disposal of SNF, however, are very sensitive issues socially. In addition, under the energy transition policy phasing out nuclear energy gradually there have been demands for alternatives so far. Thus various alternatives should need to be investigated in preparation for unexpected situations. This study has been conducted roughly in effectiveness point of view of alternative pre-managements for SNF, not pyroprocessing technology, in disposal system, consisting of three stages according to the degree of burden in disposal system. Stage I is the case for making safety increase with removing highly-mobile radionuclides from SNF. Stage II is the case for eliminating high-heat radionuclides additionally, alleviating thermal risk in the disposal system. And Stage III is the case for recovering Uranium in addition to Stage II. These options of pre-management are thought to be able to provide an intuitive strategy for effective diversification of the disposal system. Because several types of waste form from pre-management make it possible to develop the effective, newly-composed waste disposal system according to the properties of radionuclides. And the processability of SNF through pre-management might be combination with available core-drilling technology, being able to design various disposal system as well. Even though the whole, detailed unit processes have not designed yet, mass balance and distributions of radionuclides are performed under the appropriate assumption of engineering processes. As a first step the alternative approaches for SNF pre-management for disposal system might be expected to be widely used in implementing SNF management policy in the future.
임현숙(Im, Hun-Suk),김여진(Kim, Yo-Jin),홍원희(Hong, Won-Hi) 한국신재생에너지학회 2006 한국신재생에너지학회 학술대회논문집 Vol.2006 No.11
The results of simulation of direct methane fuel cell fed with liquid-state methanol feed are shown. This numerical process is based on mass and current conservation equations. The results showed that over low current density (<200mA/cm²) IV polarization curve was well-presented compared to experimental result. Methanol fed from anodic side moved into cathodic side through electrolyte membrane and the pressure near cathode electrode increased according to amount of methanol crossover and production of water. Besides change of overpotential on each el electrode were checked by x-axis.