• Journal of Energy Engineering
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• v.23 no.3
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• pp.186-190
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• 2014

Nuclear Power Plants require the control ability of chemical condition (pH) because pH control during transient accident such as LOCA makes an able the fission product removal capability to be maintained, stress corrosion cracking of stainless steel equipment to be prevented and the production of hydrogen by aluminum and zinc to be minimized. An NPP is designed to control the pH of containment spray and sump coolant using the spray additives 30% NaOH in the event of loss of coolant accident. In this paper, the pH of sump coolant of an NPP during LOCA was analyzed and the fission products removal constant and decontamination factor were calculated according to Standard Review Plan 6.5.2 related to spray chemical conditions of pH. The calculated pH value of recirculation mode using the computer code corresponds to 8.09~9.67, which meets the chemical environment regulation requirements. The fission product removal capability caused by containment spray system is performed to provide input to radiation analysis.

• Nuclear Engineering and Technology
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• v.26 no.3
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• pp.425-432
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• 1994

Voltammogram analysis of U(VI) reduction at electrochemically non-pretreated/pretreated Ti electrodes in nitric acid and hydrazine($N_2$H$_4$)/protonated hydrazine($N_2$H$_{5}$$^{＋}$) media was done in order to determine the effect of hydrazine form and Ti electrode condition on the reduction of U(VI) in nitric acid. In the case of non-pretreated Ti electrode, the reduction in nitric acid and hydrazine mono-hydrate solution needed a high activation overpotential and was affected by the ratio of hydrazine to nitric acid rather than by only absolute amount of hydrazine because of the decrease of solution conductivity and increase of iR drop, which were caused by proton consumption in the solution by the hydrazine. In the case of pretreated Ti electrode in nitric acid and protonated hydrazine solution, the reduction current peaks of U(VI) were clearer and higher enough to perform a kinetic analysis, compared with the case with the non-pretreated Ti electrode at the same potential, and the behavior was strongly affected by nitric acid. The presence of hydrazine was important in the reduction of U(VI) at the pretreated Ti electrode for preventing the reoxidation of U(IV), but the concentration of protonated hydrazine was not.t.

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 2012.11a
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• pp.32-32
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• 2012

화석연료의 남용으로 지구 온난화가 심화되어 환경과 생태계변화가 가속화되고 있고, 급속한 산업의 발달과 인류 삶의 질 향상에 따른 에너지 수요가 급증하고 있는 실정에 있으며, 일본 후쿠시마 원전사태로 원자력 에너지의 위험성으로 지구 인류환경은 심각한 국면을 맞이 하고 있어 대체 에너지의 하나로 핵융합 에너지 필요성이 증대되고 있다. 핵융합 에너지 연구 개발은 우리나라에서 KSTAR가 1997년부터 건설하기 시작하여 지난 2007년에 완공되어 지금 운용 중에 있고, 국제적으로 미국, EU, 러시아, 중국, 한국, 일본 인도가 참여하는 ITER 국제 공동프로젝트가 2004년에 건설을 시작하여 프랑스 카다라쉬에 실증 플란트를 건설 중에 있다. 이러한 핵융합 반응을 위해서는 10e-7이상의 높은 진공과 1억$^{\circ}C$ 이상에서 중수소와 삼중수소가 반응하여 발생하는 플라즈마를 제어 할 필요가 있으며, 초고온의 핵융합 플라즈마를 가두고 가동시키기 위해서는 약 12Tesla이상의 고자장 마그넷이 필요하다. 현재 ITER 실증 플란트에 사용되는 고자장 마그넷은 TF (Toroidal Field)코일과 CS (Central Field)코일에 Nb3Sn 초전도선재가 핵심부품으로 사용되고 있으며 ITER프로젝트에서는 약 850톤의 Nb3Sn 초전도선재가 사용될 전망이다. 그 중에서 일본 25%, EU, 러시아와 한국이 각각 20%, 중국7%, 미국8% 할당되어 참여국 대부분은 초전도선재를 전략적으로 공급하고 있다. 초전도 선재의 크롬도금은 1~2 마이크로미터 이하의 균일하고 얇은 도금 두께와 밀착성이 우수한 품질이 요구된다. 일반적으로 크롬도금은 산업현장에서 컨베이어 벨트 방식으로 장식이나, 내식성 및 내마모성의 특성을 필요로 할 때 사용되고 있으나, 선재에 크롬도금을 릴투릴(Reel to Reel) 방식으로 적용되는 경우는 세계적으로 아주 드물다. 핵융합 마그넷의 CICC(Conduct In Cable Conduit)도체를 만들기 위해서는 초전도선재를 이용, 3(Sc 2+OFC 1)$^*3^*5^*5^*6$형태로 연선과 케이블링을 하게 되며, 초전도 선재를 연선하고 케이블링을 할 때 크롬 도금층이 박리될 가능성이 있어 크롬도금 방법과 프로세스를 특별히 고안할 필요가 있다. ITER핵융합로 마그넷의 TF코일은 높이 14m, 폭 9m 최대자장 12Tesla, 최대전류 68kA, CICC도체 직경이 40mm로서 그 초전도 조관/도체 내부에 0.82mm 직경의 Nb3Sn 초전도 선재가 약 1350가닥으로 연선과 케이블링으로 구성되어 있다. ITER 핵융합 마그넷용 초전도 선재의 크롬도금은 마그넷 권선 후 Nb3Sn 초전도물질을 형성하기 위해서 $650^{\circ}C$에서 500시간 열처리를 실시하며 열처리 시 초전도 선재의 소선들 사이에 발생할 수 있는 소착을 방지하고, 초전도 선재에서 발생하는 AC loss를 감소시키며, Quench시 발생되는 열을 쉽게 확산시킴으로써, 초전도 마그넷의 열적 안정성(Thermal Stability) 향상과 필요에 따라서 소선간 통전울 가능하게 한다. 고려제강의 자회사인 케이에이티는 크롬도금 밀착성이 우수하고 도금두께 0.1마이크로 미터 이내 제어가 가능한 얇고 균일한 도금품질을 개발하여 한국형 핵융합 실험로인 KSTAR에 65톤 전량 공급하였고, 크롬 도금된 무산소동 선재 32톤과 초전도 선재 93톤을 전량 ITER 프로젝트에 공급하고 있으며, 2013년도 상반기에는 공급을 마무리할 예정이다.

• Nuclear Engineering and Technology
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• v.13 no.2
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• pp.85-96
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• 1981

A preliminary study of the isotope hydrology of the Han River Valley is presented. This investigation is part of a project whose overall aim is to relate the levels of heavy metal ions to the dynamics of the groundwater movement in order to establish (i) whether there is any evidence for the deterioration in groundwater quality associated with the release of industrial effluents and (ii) if so, to determine the migration path-ways. Evidence is adduced that the recharge mechanism is principally determined by the degree of urbanisation. In the metropolitan area of Seoul, river recharge dominates probably due to the combined effects of reduced infiltration and increased pumpage. In the inter-urban region, the major source of recharge is local precipitation. During the spring sampling period when the river levels were low. evidence was obtained for appreciable groundwater infiltration in the vicinity of the upstream transect. No significant correlations were observed between the levels of heavy metals in the groundwater, and the recharge mechanism, the distance from the river or the electrical conductivity of the samples.

• Nuclear Engineering and Technology
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• v.13 no.3
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• pp.145-152
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• 1981

Even though a lately reported method of high temperature exchange labelling of o-iodo-hippuric acid (Hippuran) in the absence of oxidizing agent was considered to be an attractive one, the exchange mechanism was somewhat unclear. In this study iodine isotope exchanges between o-iodohippuric acid (OIH) and radioiodide ($^{125}$ $I^{ }$) or between OIH and molecular radioiodine ($^{125}$ $I_2$) were carried out at two different temperatures. Rate constants and activation parameters were measured by applying a radio-paper chromatography technique. Since o-iodobenzoic acid is known as a by-product in the exchange labelling of OIH, data were also obtained for the OIB-iodide systems for comparison. The rate constant was increased in the order of OIB...$^{125}$ $I^{[-10]}$ >OIB...$^{125}$ $I_2$>OIH..$^{125}$ $I^{[-10]}$ >OIH...$^{125}$ $I_2$ and the activation parameters for OIH were generally larger than those for OIB :$\Delta$H$\neq$$_{OIH}$>$\Delta$H$\neq$$_{OIB}$, $\Delta$S$\neq$$_{OIH}$>$\Delta$S$\neq$$_{OIB}$. These results suggest that the mechanism of the high temperature exchange is predominantly nucleophilic even though some electrophilic character can also be involved depending upon reaction conditions. Such a fact may well be caused by a feasible formation of hydrogen bonding type transition state due probably to the ortho substituent effect of-CONHC $H_2$COOH. Thus, the high temperature exchange method is estimated to be quite effective for labelling Hippuran especially at a small research center where reducing agent-free $^{131}$ I is unavailable.ailable..

• Nuclear Engineering and Technology
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• v.27 no.2
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• pp.176-188
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• 1995

A particle tracking scheme was developed in order to model radionuclide transport through a tortuous flow Held in a rock fracture. The particle tacking method may be used effectively in a heterogeneous flow field such as rock fracture. The parallel plate representation of the single fracture fails to recognize the spatial heterogeneity in the fracture aperture and thus seems inadequate in describing fluid movement through a real fracture. The heterogeneous flow field une modeled by a variable aperture channel model after characterizing aperture distribution by a hydraulic test. To support the validation of radionuclide transport models, a radionuclide migration experiment was performed in a natural fracture of granite. $^3$$H_2O$ and $^{131}$ I are used as tracers. Simulated results were in agreement with experimental result and therefore support the validity of the transport model. Residence time distributions display multipeak curves caused by the fast arrival of solutes traveling along preferential fracture channels and by the much slower arrival of solutes following tortous routes through the fracture. Results from the modelling of the transport of nonsorbing tracer through the fracture show that diffusion into the interconnected pore space in the rock mass has a significant effect on retardation.

• Journal of Radiation Protection and Research
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• v.10 no.1
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• pp.50-63
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• 1985

A derivation of new release limit, named Derived Release Limit(DRL), into the atomsphere from a reference nuclear power plant has been performed on the basis of the new system of dose limitation recommended by the ICRP, instead of the (MPC)a limit which has been currently used until now as a general standard for radioactive effluents in Korea. In DRL Calculation, a Concentration Factor Method was applied, in which the concentrations of long-term routinely released radionuclides were in equilibrium with dose in environment under the steady state condition. The analytical model used in the exposure pathway analysis was the one which has been suggested by the USNRC and the exposure limits applied in this analysis were those recommended by the USEPA lately. In the exposure pathway analysis, all of the pathways are not considered and some may be excluded either because they are not applicable or their contribution to the exposure is insignificant compared with other pathways. In case, the environmental model developed in this study was applied to the Kori nuclear power plant as the reference power plant, the highest DRL value was calculated to be as $9.10{\times}10^6Ci/yr$ for Kr-85 in external whole body exposure from the semi-infinite radioactive cloud, while the lowest DRL value was observed 3.64Ci/yr for Co-60 in external whole body exposure from the contaminated ground, by the radioactive particulates. The most critical exposure pathway to an individual in the unrestricted area of interest (Kilchun-Ri, 1.3 km to the north of the release point) seems to be the exposure pathway from the contaminated ground and the most critical radionuclide in all pathways appears to be Co-60 in the same pathway. When comparing the actual release rate from KNU-l in 1982 with the DRL's obtained here the release of radionuclides from KNU-1 were much lower than the DRL's and it could be conclued that the exposure to an individual had been kept below the exposure limits recommended by the USEPA.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.3
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• pp.189-197
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• 2012

Geochemical composition of fracture filling minerals and groundwater was investigated to characterize geochemical characteristics of groundwater system at the KURT site. Minerals such as calcite, illite, laumontite, chlorite, epidote, montmorillonite, and kaolinite, as well as I/S mixed layer minerals were detected in the minerals extracted from the fracture surfaces of the core samples. The groundwater from the DB-1, YS-1 and YS-4 boreholes showed alkaline conditions with pH of higher than 8. The electrical conductivity (EC) values of the groundwater samples were around $200{\mu}S/cm$, except for the YS-1 borehole. Dissolved oxygen was almost zero in the DB-1 borehole indicating highly reduced conditions. The Cl- concentration was estimated around 5 mg/L and showed homogeneous distribution along depths at the KURT site. It might indicate the mixing between shallow groundwater and deep groundwater. The shallow groundwater from boreholes showed $Ca-HCO_3$ type, whereas deep groundwater below 300 m from the surface indicated $Na-HCO_3$ type. The isotopic values observed in the groundwater ranged from -10.4 to -8.2‰ for ${\delta}^{18}O$ and from -71.3 to -55.0‰for ${\delta}D$. In addition, the isotope-depleted water contained higher fluoride concentration. The oxygen and hydrogen isotopic values of deep groundwater were more depleted compared to the shallow groundwater. The results from age dating analysis using $^{14}C$ indicated relatively younger (2000~6000yr old) groundwater compared to other european granitic groundwaters such as Stripa (Sweden).

• Journal of Korea Technology Innovation Society
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• v.12 no.4
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• pp.788-818
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• 2009

Renewable energy refers to solar energy, biomass energy, hydrogen energy, wind power, fuel cell, coal liquefaction and vaporization, marine energy, waste energy, and liquidity fuel made out of byproduct of geothermal heat, hydrogen and coal; it excludes energy based on coal, oil, nuclear energy and natural gas. Developed countries have recognized the importance of these energies and thus have set the mid to long term plans to develop and commercialize the technology and supported them with drastic political and financial measures. Considering the growing recognition to the field, it is necessary to analysis up-to-now achievement of the government's related projects, in the standards of type of renewable energy, management of sectional goals, and its commercialization. Korean government is chiefly following suit the USA and British policies of developing and distributing renewable energy. However, unlike Japan which is in the lead role in solar rays industry, it still lacks in state-directed support, participation of enterprises and social recognition. The research regarding renewable energy has mainly examinedthe state of supply of each technology and suitability of specific region for applying the technology. The evaluation shows that the research has been focused on supply and demand of renewable as well as general energy and solution for the enhancement of supply capacity in certain area. However, in-depth study for commercialization and the increase of capacity in industry followed by development of the technology is still inadequate. 'Cost-benefit model for each energy source' is used in analysis of technology development of renewable energy and quantitative and macro economical effects of its commercialization in order to foresee following expand in related industries and increase in added value. First, Investment on the renewable energy technology development is in direct proportion both to the product and growth, but product shows slightly higher index under the same amount of R&D investment than growth. It indicates that advance in technology greatly influences the final product, the energy growth. Moreover, while R&D investment on renewable energy product as well as the government funds included in the investment have proportionate influence on the renewable energy growth, private investment in the total amount invested has reciprocal influence. This statistic shows that research and development is mainly driven by government funds rather than private investment. Finally, while R&D investment on renewable energy growth affects proportionately, government funds and private investment shows no direct relations, which indicates that the effects of research and development on renewable energy do not affect government funds or private investment. All of the results signify that although it is important to have government policy in technology development and commercialization, private investment and active participation of enterprises are the key to the success in the industry.