• Nuclear Engineering and Technology
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• 제50권2호
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• pp.246-252
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• 2018

A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized boiling water reactor Zircaloy-2 cladding has been performed by means of the expansion-due-to-compression (EDC) test method. The EDC method reproduces fuel pellet-clad mechanical interaction (PCMI) conditions for the cladding during RIA transients with respect to temperature and loading rates by out-of-pile mechanical testing. The tested materials had a large variation in burnup and hydrogen content (up to 907 wppm). The results of the EDC tests showed variation in the PCMI resistance of claddings with similar burnup and hydrogen content, making it difficult to clearly identify ductile-to-brittle transition temperatures. The EDC-tested samples of the present and previous work were investigated by light optical and scanning electron microscopy to study the influence of factors such as azimuthal variation of the Zr-hydrides and the presence of hydride rims and radially oriented hydrides. Two main characteristics were identified in samples with low ductility with respect to hydrogen content and test temperature: hydride rims and radial hydrides at the cladding outer surface. Crack propagation and failure modes were also studied, showing two general modes of crack propagation depending on distribution and amount of radially oriented hydrides. It was concluded that the PCMI resistance of irradiated cladding under normal conditions with homogenously distributed circumferential hydrides is high, with good margin to the RIA failure limits. To further improve safety, focus should be on conditions causing nonfavorable hydride distribution, such as hydride reorientation and formation of hydride blisters at the cladding outer surface.

• Nuclear Engineering and Technology
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• 제23권4호
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• pp.444-455
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• 1991

본 연구에서는 CANDU-PHWR 형 기존 및 개량 핵연료의 원통형 (soild) 및 환상형 소결체에 대하여, 그 핵연료 전 수명 기간동안, 반경방향 출력분포를 정확하고 신속하게 계산하는 NEDAR 모형을 개발하였다. 본 계산모형에는 핵연료소결체의 직경 범위 8.0-19.5 mm, 농축도 범위 0.71-6.0 wt % U-235이고, 계산 가능 연소도범위가 0-840 Mwh/kgU (35000MWD/T)인 한계내에서, 핵연료 반경방향 출력분포결자식 및 열중성자속감소 계산결과자료가 포함되어 있다. CAN-DU-PHWR 형 원자로 중성자속 스펙트럼을 입력자료로 하여, 로물리 전산코드, CE-HAMMER 를 이용하여 핵연료의 각 설계조건 및 소결체의 환별 국부지점에 대하여, 임의로 설정한 기준 연소시점에서 반경 방향 출력 분포를 계산하였다. 이 계산 결과를 토대로 각 환의 평균출력을 구하는 적분법 및 비선형 곡선희귀계산법에 의하여, Bessel 함수와 지수함수의 다항식으로 구성된 반경방향 출력분포 기본 결과식 및 그 계수들이 산출되었다. 본 연구에서 개발된 NEDAR 모형을 이용하여 산출한 반경방향출력분포값을, 핵연료소결체 표면에서의 값을 기본단위로 환산하여 비교하면, 본 의형에 의한 반경방향 출력분포 결과가 기존 ELESIM 전산코드의 결과에 비교하여 약간 높게 나타났다. 소결체의 반경방향의 출력 및 온도분포는 핵분열기체생성물방출과 밀접한 관계가 있으므로, 본 모형을 기존 ELESIM 전산코트의 반경방향 출력분포 계산 모형과 대체한 전산코트, 즉 KAFEPA-NEDAR에 의한 핵분열기체생 생성물방출량 예측치를 기존 ELESIM 전산코드의 예측치와 비교하였다. 여기서 KAFEPA-NEDAR리 예측치가 실험결과 자료에 보다 더 가깝게 접근하였다. 따라서, 본 연구에서 개 발된 NEDAR모형은 과대한 계산시간의 낭비없이 CANDU-PHWR 형 핵연료소결체의 반경방향출력분포를 효율적이고, 신속/정착하게 계산하는 모형임이 입증되었다.

• 대한기계학회논문집A
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• 제39권3호
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• pp.249-257
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• 2015

원자력 발전소의 반응로에는 핵분열 에너지를 생성하고 방사성 물질의 유출을 막는 핵연료 집합체가 있으며, 이러한 집합체는 핵연료와 피복관으로 구성되어 있는 핵 연료봉으로 구성되어 있다. 원자로에서 핵연료봉 거동의 안전성을 평가하기 위해 해석적인 방법을 적용하며 이러한 평가 코드를 핵 연료 성능 코드라 한다. 경수로 핵연료 해석에서는 간극의 두께에 따라 열전도도가 크게 영향을 받는 간극 열전도도가 주요 거동해석에 영향을 미친다. 본 연구에서는 간극 두께에 따라 열전도도가 변화하는 3 차원 간극 요소(Gap element)를 제안하였으며, 이를 적용하기 위해 3 차원 열탄성 모듈을 FORTRAN90을 이용하여 개발하였다. 제안된 3 차원 간극 요소를 이용하여 핵 연료봉에서 발생할 수 있는 비대칭적인 형상인 핵 연료 표면에 결함이 생긴 경우 MPS(Missing Pellet Surface)와 핵연료봉의 편심(Eccentricity of the nuclear fuel rod) 형상에 대하여 3 차원 해석을 진행하였다.

• 공업화학
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• 제23권5호
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• pp.456-461
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• 2012

본 연구에서는 바이오매스의 에너지 활용성을 확인하기 위하여 실험실 연소로를 이용한 등온 및 비등온 연소특성 연구를 수행하였으며 바이오매스의 시료로는 목재펠렛, 볏짚 및 왕겨를 사용하였다. 바이오매스의 연소시 배출가스의 특성과 분진 및 잔류물을 분석하였으며 그 결과를 RDF의 연소실험 결과와 비교분석하였다. 등온 연소특성 실험으로부터 볏짚이 다른 시료에 비하여 연소속도가 빨라 급격히 산소량이 감소되어 불완전연소율이 증가함을 확인하였으며 목재펠렛의 경우 다른 시료에 비하여 가장 낮은 $NO_{X}$ 배출농도를 나타내었다. 또한 비등온 연소특성 실험으로부터 모든 시료가 $900^{\circ}C$의 연소온도에 도달하기 이전에 연소가 대부분 일어남을 확인할 수 있었으며 $NO_{X}$의 경우 CO가 배출되는 범위와 유사한 온도범위에서 배출되는 반면에 $SO_{2}$의 경우보다 고온에서 배출됨을 확인할 수 있었다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2005년도 창립60주년 기념 추계 학술대회
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• pp.219.2-219.2
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• 2005

• 한국결정성장학회지
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• 제17권2호
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• pp.75-81
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• 2007

[ $UO_2$ ] 소결체와 $U_3O_8$종자를 5wt% 첨가한 $UO_2$ 소결체의 치밀화 과정 및 입자성장 양상을 소결 온도 및 시간을 변수로 하여 분석하였다. $UO_2$ 성형체와 5wt% $U_3O_8$ 종자 첨가 성형체를 수소분위기에서 $1300^{\circ}C$에서 $1700^{\circ}C$로 온도를 올려가며 0시간에서 4시간 소결하여 밀도와 입자크기를 측정하였다. $1300^{\circ}C$까지는 종자 첨가에 상관없이 거의 같은 밀도를 가졌지만 온도가 올라가면서 종자 첨가 소결체의 치밀화가 저하되었다가 $1700^{\circ}C$ 근처에서 거의 비슷한 밀도를 가지게 된다. 입자성장의 경우, $1600^{\circ}C$에서는 종자 입자를 제외하면 기지상의 입자 크기는 거의 비슷하지만 $1700^{\circ}C$ 이후에서는 종자첨가 $UO_2$ 소결체의 입자성장이 종자가 첨가되지 않을 경우에 비하여 2배 이상 빠르게 진행되었다.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.4052-4059
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• 2021

The microstructure of the fuel pellet plays an essential role in fission gas buildup and release and is critical for the safe and continued operation of nuclear power stations. Structural analysis of uranium dioxide (UO₂)-molybdenum (Mo) composite fuel pellets prepared at a range of sintering temperatures from 1300 to 1800 ℃ was performed. Mo micro and nanoparticles were used in making the composite pellets. A systematic investigation into the influence of processing parameters during Spark Plasma Sintering (SPS) of the pellets on the microstructure, texture, grain size, and grain boundary characters of UO₂-Mo is presented. UO₂-Mo composite show significant differences in the fraction of general boundaries and also special/coincident site lattice (CSL) boundaries. EBSD orientation maps demonstrated that <111> texturing was observed in the pellets fabricated at 1500 ℃. The experimental investigations suggest that UO₂-Mo composite pellets have favorable microstructural features compared to the UO₂ pellet.

• 한국유기농업학회지
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• 제21권3호
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• pp.335-350
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• 2013

With the efforts to development of renewable energy technologies, and increasing awareness to environmental issues, the usage of wood pallets has been increasing every year since the introduction of wood pallet technology to the domestic market. until 2009, majority usage of pellet boiler was in the residential houses. In an effort to increase the distribution of wood pellet boiler to cultivation facilities with high usage of fuels, The Ministry of Agriculture and Forestry has launched a distribution project of wood pellet boiler for fuel usage as a part of the agricultural and fishery energy efficiency projects. Although only small number of farms with a heat-culturing facility have replaced from conventional boiler to pellet boiler. Although part of reason for low usage of pallet boiler is lack of understanding and information of it, the main reasons are high initial cost and uncertainty of its cost efficiency. Also, most people from agricultural industry don't realize it's significance in terms of environmental benefit due to lack of understanding in 'resource circulation' and 'adopting to climate change'. In this study, first, we did a cost-efficiency analysis of the farm which uses a diesel boiler to grow cucumber, tomato, paprika. Then we replaced the diesel boiler to a pallet boiler and measured its cost-efficiency again. By comparing the cost-efficiency of the diesel boiler with the pellet boiler, we analyzed the economic viability of pellet boiler. Then we analyzed viability of pallet boiler usage in terms of 'resource circulation' and 'adopting to climate change'. As a result of our analysis, we have found out that under the current system of government support, the energy usage varies depends of the types crops grown and the higher the energy use, the more cost efficient it is to use the pallet boiler. Also, it is economically viable to use the pallet boiler in terms of 'resource circulation' and 'adopting to climate change'.

• Nuclear Engineering and Technology
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• 제40권1호
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• pp.21-36
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• 2008

High bum-up fuel technology has been developed through a national R&D program, which covers key technology areas such as claddings, $UO_2$ pellets, spacer grids, performance code, and fuel assembly tests. New cladding alloys were developed through alloy designs, tube fabrication, out-of-pile test and in-reactor test. The new Zr-Nb tubes are found to be much better in their corrosion resistance and creep strength than the Zircaloy-4 tube, owing to an optimized composition and heat treatment of the new Zr-Nb alloys. A new fabrication technology for large grain $UO_2$ pellets was developed using various uranium oxide seeds and a micro-doping of Al. The uranium oxide seeds, which were added to $UO_2$ powder, were prepared by oxidizing and heat-treating scrap $UO_2$ pellets. A $UO_2$ pellet containing tungsten channels was fabricated for a thermal conductivity enhancement. For the fuel performance analysis, new high burnup models were developed and implemented in a code. This code was verified by an international database and our own database. The developed spacer grid has two features of contoured contact spring and hybrid mixing vanes. Mechanical and hydraulic tests showed that the spacer grid is superior in its rodsupporting, wear resistance and CHF performance. Finally, fuel assembly test technology was also developed. Facilities for mechanical and thermal hydraulic tests were constructed and are now in operation. Several achievements are to be utilized soon by the Korea Nuclear Fuel and thereby contribute to the economy and safety of PWR fuel in Korea

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 춘계학술대회
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• pp.564-569
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• 2003

During fuel irradiation tests, all parts of cylindrical structure with multiple holes act as heat sources due to fussion heal and ${\gamma}-flux$. The high temperature is especially generated over $2500^{\circ}C$ in the center of pellet. Due to the high temperature, many problems occur, such as melting of pellet and declining of heat transfer between cladding and coolant. [n this study, it is attempted 10 minimize the temperature of pellet using optimization method about geometric variables. For thermal and optimization analysis or structure. the finite element method code. ANSYS 5.7 is used. In this procedure. subproblem approximation method is used to the optimization methods. Through the optimum design process, the temperature of sealed basket type is reduced from $2537^{\circ}C$ to $2181^{\circ}C$ and the temperature of open basket type is reduced from $2560^{\circ}C$ to $2106^{\circ}C$.