• Nuclear Engineering and Technology
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• 제25권1호
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• pp.20-27
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• 1993

이 논문은 가압경수로의 노심내 핵연료 관리용 탐색코드를 개발하기 위한 것이다. 이 목적으로 점반응도모형을 사용하여 핵연료주기 결정을 위한 FCYPRM코드를 제작하였고, 수정형 Borresen의 소격확산모형과 노달전개법에 의한 중성자 공간 해석용 CMSNAP코드를 개발하였다. 또한 수치 실험을 통하여 일련의 경험칙을 수립하고 이들을 이용하여 재장전노심 핵연료집합체 배치코드로서 ALPS코드를 개발하였다. 수치계산결과를 예시함으로서 개개 코드들의 유용성과 응용성을 입증하였으며, 이들 코드들을 가압경수로의 재장전노심 설계문제를 해결하기 위한 코드로 합성, 응용함으로서 상기 코드들이 효과적인 탐색코드가 될 수 있음을 보였다.

• 한국수소및신에너지학회논문집
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• 제32권4호
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• pp.236-244
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• 2021

Fuel cell systems for medium duty truck require high power demands under driving. Since high power demands results in significant heat generation, thermal management is crucial for the performance and durability of medium duty truck. Therefore, various configurations of dual stacks with cooling systems are investigated to understand appropriate thermal management conditions. The simulation model consists of a dynamic fuel cell stack model, a cooling system model equipped with a controller, and the mounted controller applies a feedback controller to control the operating temperature. Also, In order to minimize parasitic power, the comparison of the cooling systems involved in the arrangement was divided into three case. As a result, this study compares the reaction of fuel cells to the placement of the cooling system under a variety of load conditions to find the best placement method.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.77-82
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• 1997

The CANDU-6 transition core refuelled from 37-element fuel to CANFLEX-NU fuel has been evaluated by an 100full power day time-dependent fuel-management simulation to find the core compatibility with the CANFLEX fuel loading. The simulation calculations for the transition core were carried out with the RFSP code, provided by the cell averaged fuel properties obtained from the POWDERPUFS-V code. The simulation results were compared with those of the current 37-element fuel loading only. The results show that the CANFLEX-NU fuel bundles will be compatible with the CANDU-6 reactor because the core physics characteristics of CANFLEX-NU fuel are very similar to those of the 37-element fuel bundle.

• 방사성폐기물학회지
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• 제4권3호
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• pp.285-299
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• 2006

2005년말 현재, 전세계 32개국에서 443기의 원자력발전소가 운영되고 있다. 현재 전체발전량은 약 3,000 TWh이며 전세계 전력공급의 약 16 퍼센트를 차지하고 있다. 2004년말 사용후핵 연료는 전세계 원전의 발전용량 368 GWe에서 매년 11,000 tHM 정도 발생되고 있으며 현재 운영중인 대부분의 원전이 가동정지가 예상되는 2020년에는 445,000 tHM까지 예상되고 있다. 이러한 관점에서, 사용후핵 연료 관리는 전체 IAEA 회원국에게는 그들이 취하고 있는 후행핵 연료주기 정책과 전략에 관계없이 국제협력 등을 통해 가까운 장래에 시급히 그리고 반드시 해결해야 할 필수 사안임이 분명하다. 지난 2006년 5월 15일부터 2주간 제2차 방사성폐기물안전협약 체약국회의가 오스트리아 IAEA본부에서 개최되었다. 동 회의에서 사용후 핵연료에 대한 국가 정책 및 전략, 그리고 그들의 현황, 향후 전망, 정책에 일차적으로 고려한 인자와 이행내용 등이 심층논의되었으며, 향후 개별 국가의 노력 및 국제협력의 방향 등이 확인되었다. 본 논문에서는 상기협약에서 논의된 사용후핵 연료 관리에 대한 국가정책 및 향후 추세 둥을 자세히 기술하였다. 또한 주요국가의 최근 이행내용도 요약정리 하였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.81-81
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• 2001

• 한국품질경영학회:학술대회논문집
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• 한국품질경영학회 2010년도 춘계학술대회
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• pp.465-470
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• 2010

Korea government declared that "low carbon, green growth" through green technologies and clean energy to be the new national vision for the next 60 years(President's Liberation Day speech on Aug. 15, 2008). And succeeding "Green New Deal" plan involves nine core projects including energy saving, recycling, clean energy development. It is because hydrogen fuel cell vehicles, using electricity from chemical reaction of hydrogen and oxygen, let out water which is a by-product of such chemical reaction instead of emitting harmful particulate and gases such as NOX, SOX and CO2 that hydrogen fuel cell vehicles and its technology are drawing public attention as one of the sensible solutions in accomplishing "low carbon, green growth" agenda. Nevertheless There are many chances that let the people have a practical experience of hydrogen fuel cell vehicles. Sometimes new products, including hydrogen fuel cell vehicles, made by advanced technology can not penetrate through the market when it faces public skepticism that is stimulated from lack of knowledge and experience. That is the reason why not only cost benefit analyses and scientific risk assessments but also public acceptance studies toward hydrogen fuel cell vehicles have to be performed [Schulte, 2004]. This research address a need for comprehensive study on factors influencing public acceptance of hydrogen fuel cell car, specifically focusing on impacts of personal experience related to governmental science and technology policy toward public acceptance.

• Journal of Construction Engineering and Project Management
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• 제3권2호
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• pp.58-65
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• 2013

Earthwork activities are typically performed by heavy duty diesel (HDD) construction equipment that consumes large quantities of diesel fuel use and emits large quantities of pollutants, including nitrogen oxides (NOx), particulate matters (PM), hydrocarbon (HC), carbon monoxide (CO), and carbon dioxide ($CO_2$). This paper presents the framework for a model that can be used to estimate the production rate, activity duration, total fuel use, and total pollutants emissions for earthwork activities. A case study and sensitivity analysis for an excavator performing excavations are presented. The tool is developed by combining the multiple linear regressions (MLR) approach for modeling the productivity with the EPA's NONROAD model. The excavator data from RSMeans Heavy Construction Data were selected to build the productivity model, and emission factors of all type of pollutants from NONROAD model were used to estimate the total fuel use and emissions. The MLR model for the productivity rate can explain 92% of the variability in the data. Based on the model, the fuel use and emissions of excavator increase as the trench depth increase, but as the bucket size increase, the fuel use and emissions decrease.

• 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.

• 대한안전경영과학회지
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• 제11권3호
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• pp.49-56
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• 2009

The quantity of the fuel gas consumed is trending upwards because it can be easily delivered but isn't deteriorated and doesn't have any environmental pollution. Though there are many advantages to use the fuel gas, it can be hesitated to consume more gas because of its explosiveness and combustibility. So paying more attentions to prevent the fuel gas accidents is required. In this paper, we examine the present situation data about the fuel gas accidents and analyze them statistically using ANOVA. we confirm that there is an acceptable difference between the mean values of accidents classified by the kind of gas, the cause, the type and the place but isn't by month. It is expected that our result can be applied as preliminary data when mapping out a strategy for preventing the fuel gas accidents.

• Nuclear Engineering and Technology
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• 제49권5호
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• pp.1063-1070
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• 2017

This paper presents a method for forecasting future uranium prices that is used as input data to calculate the uranium cost, which is a rational key cost driver of the nuclear fuel cycle cost. In other words, the statistical autoregressive integrated moving average (ARIMA) model and existing engineering cost estimation method, the so-called escalation rate model, were subjected to a comparative analysis. When the uranium price was forecasted in 2015, the margin of error of the ARIMA model forecasting was calculated and found to be 5.4%, whereas the escalation rate model was found to have a margin of error of 7.32%. Thus, it was verified that the ARIMA model is more suitable than the escalation rate model at decreasing uncertainty in nuclear fuel cycle cost calculation.