• 방사성폐기물학회지
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• 제6권2호
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• pp.119-128
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• 2008

본 연구에서는 사용후핵연료 회수성과 처분밀도를 향상시킨 새로운 CANDU 사용후핵 연료처분시스템의 열해석을 수행하였다. 제안된 CANDU 사용후핵연료 처분방식 에서는 사용후핵연료의 회수성을 향상시키기 위해 일정 기간 동안 터널에 자연대류를 이용하여 저장하며, 처분밀도 향상을 위해 개선된 CAHDU 사용후핵연료 처분용기를 이용하고 있다. 제안된 CANDU 사용후핵연료 처분방식의 열적 안전성을 검토하고자 ANSYS 10.0 CFX 코드를 사용하여 시스템 전체의 정상상태 열 해석을 2단계로 나누어 수행하였다. 1단계에서는 터널간격이 처분터널 내부 온도에 미치는 영향을 분석하기 위해 터널 간격에 따른 처분터널 내벽온도 변화를 계산하였다. 계산 결과 99%의 붕괴열이 대류에 의해 냉각되는 것을 확인하였고, 이로 인해 터널 간격은 처분터널 내부 온도에 거의 영향을 주지 않았다. 2단계 계산에서는 터널간격 60 m에서 환기 설비를 고려한 처분터널의 내벽온도를 계산하였고, 이 결과는 처분터널 내부 처분용기의 표면온도를 구하기 위해 사용되었다. 계산결과, 처분용기의 표면온도는 최대 $119^{\circ}C$, 평균 $79.9^{\circ}C$로 계산되었다. 처분용기 최대온도에 따른 처분용기 내부 바스켓 피복재 최대온도는 $140.9^{\circ}C$로 계산하였으며, 이는 피복재 열적 특성을 고려하였을 때 충분한 열적 안전성을 가지고 있다고 판단되었다.

• 대한치과의사협회지
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• 제58권9호
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• pp.583-589
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• 2020

If the implant is planted in the wrong position or direction, it is disadvantageous for stress distribution, and it is easy to cause complications such as screw loosening, abutment fracture, and implant fracture. If the position or orientation of the implant is not good, efforts should be made to minimize the problem through proper implant prosthetic treatment. In this article, the prosthetic method for facilitating future maintenance in cases with poor implant placement or orientation will be presented.

• 한국지능시스템학회논문지
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• 제13권6호
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• pp.749-753
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• 2003

In this paper we introduce the concepts on retrievability, separability and connectedness of fuzzy submachines, which generalize those of crisp submachines. And also we generalize crisp primary submachines to those with fuzziness, from which we obtain the decomposition theorem of fuzzy submachines.

• The Journal of Advanced Prosthodontics
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• 제4권2호
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• pp.116-120
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• 2012

Various options have been introduced for the selection of implant overdenture attachments. Attachment wear due to the repeated insertion and removal of dentures has caused problems such as decreased retention and the requirement for suprastructure remanufacturing. In these cases, a Locator bar system was applied using the drill and tapping technique to achieve total retrievability. In a 55-year-old female patient who showed three degrees of mobility in most of her teeth due to severe alveolar bone loss, a complete denture in the maxilla and an implant supported type overdenture in the mandible were planned after extracting all the remaining teeth. Six implants were placed from canine region to the distal molar region, and the locator was connected to the milled bar using the drill and tapping technique. For a 61-year-old female edentulous patient who complained of poor retention with old denture, a complete denture in the maxilla and an implant-tissue supported type overdenture in the mandible were planned. Four implants were placed in front of mental foramen, and the Locator was also connected to the Hader bar using the drill and tapping technique. With this technique, female parts can be easily replaced, and retention can be continuously maintained.

• 방사성폐기물학회지
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• 제8권2호
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• pp.167-172
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• 2010

CANDU 사용후핵연료는 핵분열성 핵종의 농도가 비교적 낮아 장기적인 관리 방법으로서 재활용보다는 직접 처분을 고려하고 있으나 처분 부지 확보가 어려워 중간저장 정책이 단기적으로 고려되고 있다. 이와 관련하여 중간저장시설의 운영기간과 최적의 처분 착수시기에 대한 검토가 필요하다. 처분시점의 결정 요인으로는 크게 안전성, 경제성, 수용성을 설정하였다. 안전성은 크게 붕괴열과 핵비확산성 측면에서, 경제성은 각 시설의 관리비용 측면에서, 수용성은 회수성 개념 및 세대 간 책임 윤리 측면으로 나누어 검토하였다. 본 논문에서는 처분시점 결정 요인 분석 결과를 바탕으로 3가지 대안을 비교하고 최적 안을 제시하였다. 중요한 핵심 내용으로는 기술적 측면과 안전성 측면에서는 처분 시점이 빠를수록 좋다는 것과, 최적 CANDU 사용후핵연료 처분시점으로서 2041년 경을 제안하였다.

• Restorative Dentistry and Endodontics
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• 제31권4호
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• pp.323-329
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• 2006

본 실험의 목적은 새로운 레진계통의 근관 충전재로 개발된 Resilon (Epiphany, 미국 Pentron사)의 재 치료 시 제거의 용이성을 평가하는 것 이었다. 27개의 발거된 단근치를 사용하였으며, 치관부를 삭제하여 치근의 길이가 12 mm가 되도록 조정하였다. Crown-down 방법에 따라 ProFile system을 이용하여 3%의 차아염소산 나트륨 용액과 17% EDTA 용액으로 세척하면서 ISO 크기 35번, 0.04 taper ProFile이 근관장에 도달할 때까지 근관 형성을 시행하였다. 제 1군 (n = 12)은 가타퍼챠와 AH26 플러스 실러를 사용하여 열가소성 가압 충전법으로 충전 하였으며, 제 2군 (n = 15)은 같은 방법으로 제조사의 지시에 따라 Resilon으로 충전하였다. 충전 후 표본은 밀폐를 하여 습도 100%, 섭씨 37도가 유지되는 곳에 일주일간 보관하였다. 재 치료를 위하여 Gates Glidden bur와 ProFile system을 이용하여 근관 충전 물질을 제거 하였으며 이전 근관 형성 보다 한 단계 더 큰 크기의 ProFile이 근관장에 도달하는 시점까지의 시간을 기록 하였다. 최종 세척은 3% NaOCl, 17% EDTA 그리고 증류수가 사용되었다. 그 후 치아는 수직 절단하여 주사전자 현미경하에 근관의 전반적인 청결도 및 충전 물질의 잔존 정도를 치근단, 중간, 치관부로 나누어서 75배 확대상으로 평가하였다. 근관 충전 물질을 제거하는 데에 걸린 시간은 분 단위로 기록되어서 실험군 간의 차이는 Student-t 검정을 사용하여 그 유의성을 검증하였다 (오차범위 0.05 미만). 주사전자 현미경 사진은 두 명의 관찰자가 5단계로 평가하였으며 Chi-square 검정을 통해서 통계학적 유의성을 검증하였다 (오차범위 0.05 미만). 충전 후 충전재의 제거에 걸린 시간은 제 1군이 $3.25\;{\pm}\;0.32$분, 제 2 군이 $3.05\;{\pm}\;0.34$분으로 두 실험군간 통계학적으로 유의성 있는 차이가 없었다. 근관 충전재의 제거 후 근관 벽의 청결도는 두 실험 군 모두에서 치관부 1/3이 중간이나 치근단 1/3보다 우수한 결과를 보였으며 두 군 간의 차이는 없었다. 본 실험을 통해서 새로운 근관 충전 재료인 Resilon이 기존의 가타퍼챠와 실러를 사용한 충전과 비슷한 정도의 제거 용이성 및 근관 벽의 청결도를 보였음을 알 수 있었다.

• 대한치과보철학회지
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• 제40권3호
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• pp.296-305
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• 2002

The main disadvantage of cement-retained implant restorations is their difficulty in retrievability. Advocates of cemented implant restorations frequently state that retrievability of the restoration can be maintained if a provisional cement is used. The purpose of this study was to find the optimal properties of provisional luting cements and the surface treatment of abutments in single implant abutment system. 30 prefabricated implant abutments, height 8mm, diameter 6mm, 3-degree taper per side, with light chamfer margins were obtained. Three commercially available provisional luting agents which were all zinc oxide eugenol type ; Cavitec, TempBond and TempBond NE were evaluated. No cement served as the control. TempBond along with vaseline, a kind of petrolatum (2:1 ratio) was also evaluated. Ten out of thirty abutments were randomly selected and abutment surfaces were sandblasted with $50{\mu}m$ aluminum oxide. Another ten abutments were sandblasted with $250{\mu}m$ aluminum oxide. A vertical groove, 1 mm deep and 5mm long was cut in each twenty abutments. Ten of them were sandblasted with $50{\mu}m$ aluminum oxide. The full coverage casting crowns were cemented to the abutments with the designated provisional luting agent. Specimens were stored in distilled water at $37^{\circ}C$ for 24 hours. Each specimen was attached to a universal testing machine. A crosshead speed of 0.5mm/min was used to apply a tensile force to each specimen. Within the limitations of this in vitro study, the following conclusions were drawn: 1. Tensile bond strength of provisional luting cements in no surface treatment decreased with the sequence of TempBond NE, TempBond, Cavitec, TempBond with vaseline, no cement. 2. Tensile bond strength more increased by surface treatment. Sandblasting with $250{\mu}m$ aluminum oxide exhibited the highest tensile bond strength in the abutment cemented with TempBond NE and sandblasting with $50{\mu}m$ aluminum oxide exhibited the highest tensile bond strength in cemented with TempBond. 3. In the aspect of a groove formation, tensile bond strength significantly increased in TempBond with vaseline only and the others had no significant effect on tensile bond strength.

• Nuclear Engineering and Technology
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• 제45권1호
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• pp.115-124
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• 2013

Among the several options to solve PWR spent fuel accumulation problem in Korea, the dry storage method could be the most realistic and applicable solution in the near future. As the basic objectives of dry storage are to prevent a gross rupture of spent fuel during operation and to keep its retrievability until transportation, at the same time the importance of a spent fuel integrity evaluation that can estimate its condition at the final stage of dry storage is very high. According to the national need and technology progress, two representative nations of spent fuel dry storage, the USA and Japan, have established different system temperature criteria, which is the only controllable factor in a dry storage system. However, there are no technical criteria for this evaluation in Korea yet, it is necessary to review the previously well-organized methodologies of advanced countries and to set up our own domestic evaluation direction due to the nation's need for dry storage. To satisfy this necessity, building a domestic spent fuel test database should be the first step. Based on those data, it is highly recommended to compare domestic data range with foreign results, to build our own criteria, and to expand on evaluation work into recently issued integrity problems by using a comprehensive integrity evaluation code.

• Journal of Nuclear Fuel Cycle and Waste Technology
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• 제1권1호
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• pp.29-35
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• 2013

The United States Department of Energy (US DOE) is conducting research and development (R&D) activities under the Used Fuel Disposition Campaign (UFDC) to support storage, transportation, and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. R&D activities are ongoing at nine national laboratories, and are divided into storage, transportation and disposal. Storage R&D focuses on closing technical gaps related to extended storage of UNF. Transportation R&D focuses on ensuring transportability of UNF following extended storage, and addressing data gaps regarding nuclear fuel integrity, retrievability, and demonstration of subcriticality. Disposal R&D focuses on identifying geologic disposal options and addressing technical challenges for generic disposal concepts in mined repositories in salt, clay/shale, and granitic rocks, and deep borehole disposal. UFDC R&D goals include increasing confidence in the robustness of generic disposal concepts, reducing generic sources of uncertainty that may impact the viability of disposal concepts, and developing science and engineering tools to support the selection, characterization, and licensing of a repository. The US DOE has also initiated activities in the Nuclear Fuel Storage and Transportation (NFST) Planning Project to facilitate the development of an interim storage facility and to support transportation infrastructure in the near term.

• Nuclear Engineering and Technology
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• 제46권1호
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• pp.73-80
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• 2014

A concrete cask is an option for spent nuclear fuel interim storage. A concrete cask usually consists of a metallic canister which confines the spent nuclear fuel assemblies and a concrete overpack. When the overpack undergoes a missile impact, which might be caused by a tornado or an aircraft crash, it should sustain an acceptable level of structural integrity so that its radiation shielding capability and the retrievability of the canister are maintained. A missile impact against a concrete overpack produces two damage modes, local damage and global damage. In conventional approaches [1], those two damage modes are decoupled and evaluated separately. The local damage of concrete is usually evaluated by empirical formulas, while the global damage is evaluated by finite element analysis. However, this decoupled approach may lead to a very conservative estimation of both damages. In this research, finite element analysis with material failure models and element erosion is applied to the evaluation of local and global damage of concrete overpacks under high speed missile impacts. Two types of concrete overpacks with different configurations are considered. The numerical simulation results are compared with test results, and it is shown that the finite element analysis predicts both local and global damage qualitatively well, but the quantitative accuracy of the results are highly dependent on the fine-tuning of material and failure parameters.