• Nuclear Engineering and Technology
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• 제15권4호
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• pp.280-285
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• 1983

핵분열 중성자스펙트럼이 원자로핵계산에 미치는 영향을 고속임계로심의 임계계산을 통해 다각적으로 분석하였다. 검토된 내용은 Maxwell식과 Watt-Cranberg 형의 식 적용, 영역별 스펙트럼자료의 적용, Maxwell식에서 핵온도 선정에 따른 효과, 우라늄과 풀루토늄의 가중평균된 스펙트럼자료의 적용, 노심내 전에너지에 따른 핵온도를 고려한 스펙트럼자료의 적용 등이다.

• Composites Research
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• 제28권2호
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• pp.70-74
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• 2015

본 논문에서는 탄소나노튜브(CNT)와 마이크로 글래스 버블(GB)을 포함한 폴리아마이드 6(PA6) 복합재의 열전 특성을 다뤘다. 복합재에 포함된 GB은 복합재 내에서 큰 공간을 차지하게 되는데, 이때 CNT는 GB가 없는 공간으로 밀려나면서 고밀도로 격리된(segregated) 네트워크를 형성한다. CNT의 분산을 위해, 소니케이션(Sonicatoin)으로 CNT를 분산시킨 PA6, 포름산 용액을 증류수를 이용하여 응고시킨 후 압축성형하여 복합재 판을 제조하였다. 복합재 판의 열전성능을 평가하기 위해서 열전도도, 전기전도도, 제벡계수(Seebeck coefficient) 등을 측정하였고, 최고 0.016의 성능지수를 얻었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.899-905
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• 1998

The analysis priority makings the recommendation to reduce the total core damage frequency (CDF) of Wolsong nuclear Power Plant nits 2/3/4 was Performed in this paper. In order to derive the recommendation, the sensitivity analysis of CDF on which major contributors effect m performed based on the accident quantification results during Level 1 Probabilistic safety assessment (PSA). Priorities were ranked in tile way that compares the CDF reduction rate with efforts required to implement those recommendations using risk matrix

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.954-962
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• 2019

It is well known that the variance of tally is biased in a Monte Carlo calculation based on the power iteration method. Several studies have been conducted to estimate the real variance. Among them, the batch method, which was proposed by Gelbard and Prael, has been utilized actively in many Monte Carlo codes because the method is straightforward, and it is easy to implement the method in the codes. However, there is a problem when utilizing the batch method because the estimated variance varies depending on batch size. Often, the appropriate batch size is not realized before the completion of several Monte Carlo calculations. This study recognizes this shortcoming and addresses it by permitting selection of an appropriate batch size.

• Nuclear Engineering and Technology
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• 제41권1호
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• pp.107-112
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• 2009

Corrosion of nickel-base alloys (Hastelloy C-276, Inconel 625, and Inconel X-750) in $500^{\circ}C$, 25MPa supercritical water (with 10 wppb oxygen) was investigated to evaluate the suitability of these alloys for use in supercritical water reactors. Oxide scales formed on the samples were characterized by gravimetry, scanning electron microscopy/energy dispersive spectroscopy, X-ray diffraction, and X-ray photoelectron spectroscopy. The results indicate that, during the 1000h exposure, a dense spinel oxide layer, mainly consisting of a fine Cr-rich inner layer ($NiCr_{2}O_{4}$) underneath a coarse Fe-rich outer layer ($NiFe_{2}O_{4}$), developed on each alloy. Besides general corrosion, nodular corrosion occurred on alloy 625 possibly resulting from local attack of ${\gamma}$" clusters in the matrix. The mass gains for all alloys were small, while alloy X -750 exhibited the highest oxidation rate, probably due to the absence of Mo.

• Nuclear Engineering and Technology
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• 제45권4호
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• pp.565-572
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• 2013

The fabrication methods and requirements of the fiber, interphase, and matrix of nuclear grade $SiC_f/SiC$ composites are briefly reviewed. A CVI-processed $SiC_f/SiC$ composite with a PyC or $(PyC-SiC)_n$ interphase utilizing Hi-Nicalon Type S or Tyranno SA3 fiber is currently the best combination in terms of the irradiation performance. We also describe important material issues for the application of SiC composites to LWR fuel cladding. The kinetics of the SiC corrosion under LWR conditions needs to be clarified to confirm the possibility of a burn-up extension and the cost-benefit effect of the SiC composite cladding. In addition, the development of end-plug joining technology and fission products retention capability of the ceramic composite tube would be key challenges for the successful application of SiC composite cladding.

• 방사성폐기물학회지
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• 제21권2호
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• pp.247-253
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• 2023

According to NSSC Notice No. 2021-10, safety analysis needs to be introduced in the decommissioning plan. Public and occupational dose analyses should be conducted, specifically for unexpected radiological accidents. Herein, based on the risk matrix and analytic hierarchy process, the method of selecting accident scenarios during the decommissioning of nuclear power plants has been proposed. During decommissioning, the generated spent resin exhibits relatively higher activity than other generated wastes. When accidents occur, the release fraction varies depending on the conditioning method of radioactive waste and type of radioactive nuclides or accidents. Occupational dose analyses for 2 (fire and drop) among 11 accident scenarios have been performed. The radiation doses of the additional exposures caused by the fire and drop accidents are 1.67 and 4.77 mSv, respectively.

• Nuclear Engineering and Technology
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• 제35권5호
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• pp.369-377
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• 2003

Since Zr-2.5Nb pressure tubes have a high risk for the formation of blisters during their operation in pressurized heavy water reactors, there has been a strong incentive to develop a method for the non-destructive detection of blisters grown on the tube surfaces. However, because there is little mismatch in acoustic impedance between the hydride blisters and zirconium matrix, it is not easy to distinguish the boundary between the blister and zirconium matrix with conventional ultrasonic methods. This study has focused on the development of a special ultrasonic method, so called ultrasonic velocity ratio method for a reliable detection of blisters formed on Zr-2.5Nb pressure tubes. Hydride blisters were grown on the outer surface of the Zr-2.5Nb pressure tube using a cold finger attached to a steady state thermal diffusion equipment. To maximize a difference in the ultrasonic velocity in hydride blisters and the zirconium matrix, the ultrasonic velocity ratio of longitudinal wave to shear wave, $V_L/V_S$, has been determined based on the flight time of the longitudinal echo and reflected shear echo from the outer surface of the tubes. The feasibility of the ultrasonic velocity ratio method is confirmed by comparing the contour plots reproduced by this method with those of the blisters grown on the Zr-2.5Nb pressure tubes.

• Nuclear Engineering and Technology
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• 제20권3호
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• pp.197-202
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• 1988

장기 용출율을 예측하기 위하여 유한 격판 근사 방법이 개발되었다. 이 방법은 폐기물 고화체에서의 방사성 동위원소 확산 특성이 고화체 형태에 관련되지 않고 체적/면적비 (V/S)와 확산계수에만 의존한다는 가정에 근거하고 있다. 결과적으로 용출율은 동일 체적/면적비를 갖는 유한 격판을 기술하는 방정식의 해로 표시할 수 있다. 유한 격판 근사 방법을 사용한 계산 결과는 유한 원통과 유한 구형에 관한 확산 해석에 관한 해와 비교되었다. 여기서 도출된 단순 모델은 다른 모델과의 비교 결과 잘 일치하고 있고 방사성 핵종의 용출 현상에 관한 장기 예측에 전반적인 응용이 가능한 것을 보여준다.

• 한국진공학회지
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• 제12권S1호
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• pp.63-66
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• 2003

It is experimentally shown that a $TiO_2$ film on Si(111) substrate was prepared by using the technique of D.C. reaction sputter deposition with $Ar^{+}$ ion beam bombardment, and a layer-like structure was observed from the depth profile of the interface between $TiO_2$ film and Si substrate with Scanning Electron Microscopy and Electron Probe. It was also surprisingly discovered that Ti atoms could be detected at about 9 $\mu$m depth. The $TiO_2$-Si interface bombarded by $Ar^{+}$ ion beams revealed multi-layer structures, a mechanism might be caused by defect diffusion, impurity and matrix relocation. Multi-relocations of impurity and matrix atoms were as a result of profile broadening of the $TiO_2$-Si interface, and the spread due to matrix relocation in this system is shown to exceed much more the spread due to impurity relocation.