• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.476-482
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• 1996

사용후핵연료 관리 및 후행핵연료주기 시설에서 요구되는 사용후핵연료 연료봉 인출기술을 확보하기 위하여 연료봉 인출장치를 제작하였으며, 모의 연료봉을 사용하여 이를 인출하는 실험을 수행하여 장치의 성능을 시험하였다. 인출장치는 컴퓨터로 제어할 수 있도록 함으로서 대부분의 인출공정을 자동으로 수행할 수 있도록 하였다. 실험 결과를 분석하여 장치의 개선점을 제시하였고, 또한 향후 실제 사용후핵연료 시설에 적용할 경우에 대비한 보완책도 제시하였다.

• 대한방사선방어학회:학술대회논문집
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• 2009.04a
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• pp.208-209
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• 2009

• Proceedings of the KSME Conference
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• 2005.11a
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• pp.219.2-219.2
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• 2005

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.177-178
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• 2016

전처리 공정장치 구축에 앞서 정확한 설계와 검증이 선행되어야 한다. 우선 디지털 목업 기술을 통해 설계검증을 철저히 함으로써 공정의 품질을 높이고 공정하자를 최소화 할 수 있다. 전처리 공정 중 사용후핵연료봉 인출 핵심장치의 유지보수를 쉽게 하고, 원격제어 효율을 높이기 위한 모듈화와 그에 대한 모듈화 방안분석을 수행하였다. 이를 위해해 전처리 디지털 목업 시스템 검증 대상과 사용 후핵연료봉 인출 핵심장치 주요모듈을 선정하였으며, 주요 모듈의 모듈화 방안 과 모듈 탈착 시간 검증하였다. 그 결과, 사용후핵연료봉 인출 핵심장치에서는 5개의 주요 모듈로 구성하였으며, 모듈 탈착 시간 검증에서 작업시간은 클램프모듈이 약 190초, 언볼팅, 푸셔 모듈이 140초, 인출 모듈이 160초, 연료봉 밀집 모듈이 80초 소요될 것 분석되었다. 향후 전처리장치별 모듈 분석과 LAYOUT 운영을 포함해서 MSM 시뮬레이터의 디바이스 및 시뮬레이터 시스템 구축을 수행할 것이다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.207-212
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• 1996

DUPIC 핵연료 제조를 위해서 PWR 사용후핵연료의 피복관과 소결체를 분리하는 방법이 검토되었다. 약 50 cm의 PWR 사용후핵연료의 길이방향에 일정한 간격으로 구멍을 뚫어 산화하는 방법, 10∼20 m의 길이로 핵연료봉을 절단하여 산화하는 방법, 그리고, 핵연료봉의 길이 방향에서 피복관을 slitting하여 산화하는 방법에 대해 실험을 수행하였다. 실험 결과들로 보아 DUPTC 핵연료 제조 공정에 가장 적합한 방법으로는 핵연료봉 길이방향으로 slitting하여 산화하는 것이 가장 타당한 것으로 판명되었다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.4
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• pp.287-297
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• 2014

For several decades, many countries operating nuclear power plants have been studying the various disposal alternatives to dispose of the spent nuclear fuel or high-level radioactive waste safely. In this paper, as a direct disposal of spent nuclear fuels for deep geological disposal concept, the rod consolidation from spent fuel assembly for the disposal efficiency was considered and analyzed. To do this, a concept of spent fuel rod consolidation was described and the related concepts of disposal canister and disposal system were reviewed. With these concepts, several thermal analyses were carried out to determine whether the most important requirement of the temperature limit for a buffer material was satisfiedin designing an engineered barrier of a deep geological disposal system. Based on the results of thermal analyses, the deposition hole distance, disposal tunnel spacing and heat release area of a disposal canister were reviewed. And the unit disposal areas for each case were calculated and the disposal efficiencies were evaluated. This evaluation showed that the rod consolidation of spent nuclear fuel had no advantages in terms of disposal efficiency. In addition, the cooling time of spent nuclear fuels from nuclear power plant were reviewed. It showed that the disposal efficiency for the consolidated spent fuel rods could be improved in the case that cooling time was 70 years or more. But, the integrity of fuels and other conditions due to the longer term storage before disposal should be analyzed.

• Journal of the Korean Society for Nondestructive Testing
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• v.27 no.5
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• pp.432-441
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• 2007

Image processing methods for an extraction of a nuclear fuel rod image and visualization methods of the RGB color data were studied with a sectional image of spent fuel assembly. The fuel rod images could be extracted by using a histogram analysis, an edge detection and RGB rotor data. In these results, a size of the spent fuel assembly could be measured by using a histogram analysis method and a shape of the spent fuel rod could be observed by using an edge detection method. Finally, a various analyses were established for status of the spent fuel assembly by realized various 3D images for the color data in an image of a spent fuel assembly.

• Journal of the Korean Society for Nondestructive Testing
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• v.22 no.1
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• pp.9-13
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• 2002

A pool image processing measurement method has been developed to improve the examination efficiency and to minimize the errors of dimensional measurements of spent fuel assemblies in pool. Diameter and length measurements of mock-up fuel rods using the image processing system are $-0.24{\pm}0.03mm,\;0.34{\pm}0.06mm$ on the basis of the true value and their maximum errors are within -0.3 and 0.4mm, respectively, According to the result of dimensional measurement of spent fuels in pool, the upper and lower part diameter and mid part diameter of fuel rods of the J44 fuel assembly irradiated for 2 cycles in the Kori-2 nuclear reactor were decreased by about 2.0 and 3.0% in comparison with design values, respectively. The length of fuel rods was elongated by about 0.4%. The change behavior of diameter and length. of fuel rods of the F02 fuel assembly irradiated for 3 cycles in the Kori-1 nuclear reactor showed a trend similar to the results of J44.

• Nuclear Engineering and Technology
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• v.25 no.3
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• pp.424-429
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• 1993

Numeric characters are printed at the end part of nuclear fuel rod containing nuclear pellets. Fuel rods are discriminated and managed systematically by these characters in the process of producing fuel assembly. The characters are also used to examine manufacturing process of fuel rods in the survey of burnup efficiency as well as in inspection of irradiated fuel rod. Therefore automatic character recognition is one of the most important technologies in automatic manufacture of fuel assembly. In this study, character recognition system is developed. In the developed system, mesh feature extracted from each character written in the fuel rod has been compared with reference feature value stored in database, and the character is thus identified. In the result of experiment, 95.83 percent recognition rate is achievable.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.2
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• pp.149-156
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• 2016

The spent fuel stored in the pool is vulnerable to external impacts, since the severe reactor conditions degrade the structural integrity of the fuel. Therefore an accident during shipping and handling should be considered. In an extreme case, the fuel assembly drop can be happened accidentally during handling the nuclear fuel in the spent fuel pool. The rod failure during such drop accident can be evaluated by calculating the impact force acting on the fuel assembly at the bottom of the spent fuel pool. The impact force can be evaluated with the impact velocity at the bottom of the spent fuel pool. Since fuel rods occupies most of weight and volume of a nuclear fuel assembly, the information of the rods are important to estimate the hydraulic resistance force. In this study, the hydraulic force acting on the $3{\times}3$ short rod bundle model during the drop accident is calculated, and the result is verified by comparing the numerical simulations. The methodology suggested by this study is expected to be useful for evaluating the integrity of the spent fuel.