• 방사선산업학회지
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• 제17권4호
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• pp.457-469
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• 2023

The clearance level by nuclide is announced by the Nuclear Safety and Security Commission. However, the clearance level of uranium existing in nature has not been announced, and research is needed. Therefore, the purpose of this study was to evaluate the clearance level of uranium nuclides appropriate to domestic conditions preliminary. For this purpose, this study selected major processes for recycling metal wastes and analyzed the exposure scenarios and major input factors by investigating the characteristics of each process. Then, the radiation dose to the general public and workers was evaluated according to the selected scenarios. Finally, the results of the radiation dose per unit radioactivity for each scenario were analyzed to derive the clearance level of uranium in metal waste. The results of the radiation dose assessment for both the general public and workers per unit radioactivity of uranium isotopes were shown to meet the allowable dose (individual dose of 10 µSv y^-1 and collective dose of 1 Man-Sv y^-1) regulated by the Nuclear Safety and Security Commission. The most conservative scenarios for volumetric and surface contamination were evaluated for the handling of the slag generated after the melting of the metal waste and the direct reuse of the contaminated metal waste into the building without further disposal. For each of these scenarios, the radioactivity concentration by uranium isotope was calculated, and the clearance level of uranium in metal waste was calculated through the radioactivity ratio by enrichment. The results of this study can be used as a basic data for defining the clearance level of uranium-contaminated radioactive waste.

• 전기화학회지
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• 제17권1호
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• pp.44-48
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• 2014

양성자교환막연료전지에서 사용할 탄화수소계 전해질 막 (술폰산화 폴리아릴렌에테르설폰)의 산화안정성을 향상시키기 위하여 세륨이온이 도입된 전해질 복합막을 제조하였다. 세륨이온의 함유 농도에 따른 산화안정성의 변화를 관찰하였고, 함수율 및 수소이온전도도에 미치는 영향을 조사하였다. ICP 분석을 통해 세륨이온의 함침여부를 검증하였고, NMR 피크의 화학적 이동으로 금속이온과 술폰산 그룹과의 배위여부를 확인하였다. 세륨이온의 함량이 증가함에 따라 이온전도도 및 함수율은 감소하였으나, 산화안정성은 향상되었다. 특히, 과산화수소폭로 가속화장치를 이용하여, 기존의 펜톤산화실험에 비해 실제 연료전지운전과 매우 유사한 조건에서 전해질 막의 산화안정성을 평가하였다.

• 한국산학기술학회논문지
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• 제15권5호
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• pp.2553-2558
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• 2014

회전익 항공기 중 군에서 운용하는 기동헬기는 전장상황에서 운용되기 때문에 연료셀 피탄 시 발생 가능한 상황을 예측하여 설계에 반영해야 한다. 연료셀 설계 고려사항은 피탄 상황의 연료셀 내부 압력, 충격파에 의한 연료셀 자체 및 금속 피팅부 응력, 탄의 운동에너지 등이 포함될 수 있다. 중요 설계데이타 확보를 위해서는 실물 연료셀을 이용한 입증시험을 수행하는 것이 가장 좋은 방법이다. 그러나, 극한조건하의 입증시험은 상당한 비용과 시간이 요구되며, 실패 위험성도 높다. 따라서, 실물을 이용한 시험을 수행하기 전 시행착오의 가능성을 줄이기 위해서는 다양한 수치해석을 통해 연료셀 내부압력과 응력 등의 설계 데이타 예측이 반드시 필요하다. 본 연구에서는 입자법을 사용하여 연료셀의 중요 입증시험 중 하나인 피탄시험에 대한 수치해석을 수행하였다. 수치해석은 전용 충돌해석 프로그램인 LS-DYNA를 사용하였고, 피탄의 영향으로 연료셀 내부 압력은 350~360MPa, 수압램에 의한 굽힘하중으로 260~350MPa의 등가응력이 금속피팅부에 발생하는 것으로 파악되었다.

• 에너지공학
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• 제17권1호
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• pp.38-45
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• 2008

본 연구는 캐나다산 아사바스카 오일샌드 역청(Athabasca Oilsands Bitumen)의 용매 불용분 실험(Solvent-Insolubles Experiment)을 통하여 아스팔텐(Asphaltenes : Solvent-Insolubles) 및 말텐(Maltenes : Solvent-Solubles)에 대한 다양한 물리 화학적 특성변화를 살펴보기 위하여 수행되었다. 용매는 n-Heptane, n-Hexane, n-Pentene의 3가지 용매를 사용하였고, 아스팔텐의 분리는 ASTM D 3279 방법을 응용하여 실시하였다. 역청, 아스팔텐, 말렌에 대한 분석항목은 원소분석, 분자량 분포, 비점 분포, 중금속 함량, API 비중, 점도, SARA 분포 등이다. 분석 결과 모든 말텐의 황 함량, 중금속 함량 및 분자량은 역청에 비하여 낮은 경향을 보였다. 그리고 n-Pentane 용매를 사용한 경우가 다른 용매에 비하여 말텐의 점도가 감소하였고, 황, 중금속 함량 및 분자량도 상대적으로 낮게 측정되었다. 따라서, 본 실험결과는 합성원유(SCO) 생산을 위한 역청의 경질화 공정에 필요한 기초자료로 활용할 수 있다고 판단된다.

• 방사선산업학회지
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• 제18권1호
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• pp.43-52
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• 2024

Currently, there are no interim storage facilities and permanent disposal facilities in Korea, so all spent nuclear fuels are temporarily stored. However, the temporary storage facility is approaching saturation, and as a measure to this, the 2nd Basic Plan for the Management of High-Level Radioactive Waste presented an operation plan for dry interim storage facilities and dry temporary storage facilities on the NPP on-site. The dry storage can be operated in various ways, and to select the optimal dry storage method, the reduction of exposure for workers must be considered. Accordingly, it is necessary to develop a worker exposure scenario according to the dry storage method and evaluate and compare the radiological impact for each method. The purpose of this study is to develop an exposure scenario for workers transporting spent nuclear fuel by dry storage method. To this end, first, the operation procedure of the foreign commercial spent nuclear fuel dry storage system was analyzed based on the Final Safety Analysis Report (FSAR). 1) the concrete overpack-based system, 2) the metal overpack-based system, and 3) the vertical storage module-based system were selected for analysis. Factors were assumed that could affect the type of work (working distance, working hours, number of workers, etc.) during transportation work. Finally, the work type of the processes involved in transporting spent nuclear fuel by dry storage method was set, and an exposure scenario was developed accordingly. The concrete overpack method, the metal overpack method, and the vertical storage module method were classified into a total of 31, 9, and 23 processes, respectively. The work distance, work time, and number of workers for each process were set. The product of working hours and number of workers (Man-hour) was set high in the order of concrete overpack method, vertical storage module method, and metal overpack method, and short-range work (10 cm) was most often applied to the concrete overpack method. The results of this study are expected to be used as basic data for performing radiological comparisons of transport workers by dry storage method of spent nuclear fuel.

• Nuclear Engineering and Technology
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• 제53권10호
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• pp.3367-3378
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• 2021

The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for the improvement of fuel pin performance codes, in particular the enhancement of their predictive capabilities towards uranium-plutonium mixed oxide fuels and stainless-steel cladding under irradiation in fast reactor environments. To this end, the current capabilities of fuel performance codes must be critically assessed against experimental data from available irradiation experiments. This work is devoted to the assessment of three European fuel performance codes, namely GERMINAL, MACROS and TRANSURANUS, against the irradiation of two fuel pins selected from the SUPERFACT-1 experimental campaign. The pins are characterized by a low enrichment (~ 2 wt.%) of minor actinides (neptunium and americium) in the fuel, and by plutonium content and cladding material in line with design choices envisaged for liquid metal-cooled Generation IV reactor fuels. The predictions of the codes are compared to several experimental measurements, allowing the identification of the current code capabilities in predicting fuel restructuring, cladding deformation, redistribution of actinides and volatile fission products. The integral assessment against experimental data is complemented by a code-to-code benchmark focused on the evolution of quantities of engineering interest over time. The benchmark analysis points out the differences in the code predictions of fuel central temperature, fuel-cladding gap width, cladding outer radius, pin internal pressure and fission gas release and suggests potential modelling development paths towards an improved description of the fuel pin behaviour in fast reactor irradiation conditions.

• 한국자동차공학회논문집
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• 제7권6호
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• pp.106-114
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• 1999

Today, one of the most important objective in automobile development is to reduce the weight of automobile . The eventual depletion of petroleum and environmental regulations brought considerable emphasis to this area on increasing fuel efficiency. Conventional intake air-fuel system is very heavy because it is composed of numerous parts. The bulky size caused increase in the amount of metal being used to build automobile chassis and this became a serious weight problem. The size also caused difficulties in optimization of fuel supply system which in turn decreased engine efficiency. Currently , there are efforts to integrate several intake system modules into one. The purpose of this paper is to evaluate the directions of such development.

• Nuclear Engineering and Technology
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• 제52권4호
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• pp.689-699
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• 2020

In this work, new multi-recycling options of TRU nuclides using PWR fuel assemblies comprised of MOX and FCM (Fully Ceramic Micro Encapsulated) fuels are suggested and neutronically analyzed. These options do not use a fully recycling of TRU but a partial recycling where TRUs from MOX fuels are recycled while the ones from FCM fuels are not recycled due to their high consumption rate resulted from high burnup. In particular, additional external TRU feed in MOX fuels for each cycle was considered to significantly increase the TRU consumption rate and the finally selected option is to use external TRU and enriched uranium feed as a makeup for the heavy metal consumption in MOX fuels. This hybrid external feeding of TRU and enriched uranium in MOX fuel was shown to be very effective in significantly increasing TRU consumption rate, maintaining long cycle length, and achieving negative void reactivity worth during recycling.

• 한국세라믹학회지
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• 제42권12호
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• pp.865-871
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• 2005

Submicron thick solid electrolyte membrane is essential to the implementation of low temperature solid oxide fuel cell, and, therefore, development of new electrode structures is necessary for the submicron thick solid electrolyte deposition while providing functions as current collector and fuel transport channel. In this research, a nickel membrane with multi-stage nano hole array has been produced via modified two step replication process. The obtained membrane has practical size of 12mm diameter and $50{\mu}m$ thickness. The multi-stage nature provides 20nm pores on one side and 200nm on the other side. The 20nm side provides catalyst layer and $30\~40\%$ planar porosity was measured. The successful deposition of submicron thick yttria stabilized zirconia membrane on the substrate shows the possibility of achieving a low temperature solid oxide fuel cell.

• 전기화학회지
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• 제16권1호
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• pp.52-58
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• 2013

고분자 전해질 연료전지(Polymer Electrolyte Membrane Fuel Cell, PEMFC) 상용화를 위해 해결해야 할 과제 중의 하나인 가격 저감을 이루기 위한 방법으로 백금 촉매를 대신할 비귀금속(non-precious metal) 촉매 제조에 관한 연구를 수행하였다. 비귀금속 촉매의 합성은 산소환원반응(oxygen reduction reaction, ORR)의 활성점으로 알려져 있는 코발트-질소(Co-N) 결합을 형성하기 위해 질소를 포함하는 폴리아닐린(PANI)과 코발트염(Co precursor), 그리고 카본 블랙(C)을 일정한 비율대로 혼합한 후 특별한 열처리 과정 없이 단순한 화학적 환원법에 제조되었다. 제조된 Co-PANI-C 복합 촉매의 구조 분석을 위해 X-선 회절분석(X-ray diffraction, XRD)과 열중량분석(thermogravimetric analysis, TGA)을 실시하였고, ORR에 대한 활성을 평가하기 위해 rotating disk electrode(RDE) 및 rotating ring disk electrode(RRDE) 측정을 수행하였다. 그 결과 Co-PANI-C 복합 촉매는 ORR반응에 대한 개시 전압은 백금 촉매보다 60 mV 밖에 낮지 않은 값을 보였지만, 반응에 의해 발생되는 환원 전류는 여전히 백금 촉매보다 낮은 값을 보였다. 이 밖에도 전극 회전 속도에 따른 ORR 특성 변화, 전압 사이클 회수에 따른 내구성 변화, 연료전지 적용 시 성능 변화에 대해 논의할 것이다.