• 제목/요약/키워드: Nuclear Cost

검색결과 637건 처리시간 0.033초

Preliminary Conceptual Design and Cost Analysis of the DUPIC Fuel Fabrication Plant

  • Park, Jongwon;Wonil Ko;Lee, Jaesol;Inha Jung;Park, Hyunsoo
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(3)
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    • pp.441-446
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    • 1996
  • A preliminary conceptual design of the DUPIC fuel fabrication plant with production capacity of 400 MTHE/yr is presented. Capital and operating costs are also included. The levelized unit fabrication cost (LUC) for a reference mode was estimated at $509/kgHE, and sensitivity of some variable parameters to this reference was analysed.

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원자력 발전소의 최적 운행중지 시기 결정 방법 (Deciding the Optimal Shutdown time of a Nuclear Power Plant)

  • 양희중
    • 산업공학
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    • 제13권2호
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    • pp.211-216
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    • 2000
  • A methodology that determines the optimal shutdown time of a nuclear power plant is suggested. The shutdown time is decided considering the trade off between the cost of accident and the loss of profit due to the early shutdown. We adopt the bayesian approach in manipulating the model parameter that predicts the accidents. We build decision tree models and apply dynamic programming approach to decide whether to shutdown immediately or operate one more period. The branch parameters in decision trees are updated by bayesian approach. We apply real data to this model and provide the cost of accidents that guarantees the immediate shutdown.

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Utility of Nuclear Morphometry in Effusion Cytology

  • Ambroise, Marie Moses;Jothilingam, Prabhavati;Ramdas, Anita
    • Asian Pacific Journal of Cancer Prevention
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    • 제15권16호
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    • pp.6919-6922
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    • 2014
  • Background: The cytological analysis of serous effusions is a common investigation and yields important diagnostic information. However, the distinction of reactive mesothelial cells from malignant cells can sometimes be difficult for the cytopathologist. Hence cost-effective ancillary methods are essential to enhance the accuracy of cytological diagnosis. The aim of this study was to examine the utility of nuclear morphometry in differentiating reactive mesothelial cells from malignant cells in effusion smears. Materials and Methods: Sixty effusion smears consisting of 30 effusions cytologically classified as malignant (adenocarcinomas) and 30 benign effusions showing reactive mesothelial cells were included in the study. ImageJ was used to measure the nuclear area, perimeter, maximal feret diameter, minimal feret diameter and the circularity. A total of ten representative cells were studied in each case. Results: Significant differences were found between benign and malignant effusions for the nuclear area, perimeter, maximal feret diameter and minimal feret diameter. No significant difference was found for circularity, a shape descriptor. Receiver operating characteristic (ROC) curve analysis revealed that nuclear area, perimeter, maximal feret diameter, and minimal feret diameter are helpful in discriminating benign and malignant effusions. Conclusions: Computerised nuclear morphometry is a helpful ancillary technique to distinguish benign and malignant effusions. ImageJ is an excellent cost effective tool with potential diagnostic utility in effusion cytology.

Efficiency criteria for optimization of separation cascades for uranium enrichment

  • Sulaberidze, Georgy;Zeng, Shi;Smirnov, Andrey;Bonarev, Anton;Borisevich, Valentin;Jiang, Dongjun
    • Nuclear Engineering and Technology
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    • 제50권1호
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    • pp.126-131
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    • 2018
  • As it is known, uranium enrichment is carried out on industrial scale by means of multistage separation facilities, i.e., separation cascades in which gas centrifuges (GCs) are connected in series and parallel. Design and construction of these facilities require significant investment. So, the problem of calculation and optimization of cascade working parameters is still relevant today. At the same time, in many cases, the minimum unit cost of a product is related to the cascade having the smallest possible number of separation elements/GCs. Also, in theoretical studies, it is often acceptable to apply as an efficiency criterion the minimum total flow to supply cascade stages instead of the abovementioned minimum unit cost or the number of separation elements. In this article, cascades with working parameter of a single GC changing from stage to stage are optimized by two of the abovementioned performance criteria and are compared. The results obtained allow us to make a conclusion about their differences.

Exergetic design and analysis of a nuclear SMR reactor tetrageneration (combined water, heat, power, and chemicals) with designed PCM energy storage and a CO2 gas turbine inner cycle

  • Norouzi, Nima;Fani, Maryam;Talebi, Saeed
    • Nuclear Engineering and Technology
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    • 제53권2호
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    • pp.677-687
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    • 2021
  • The tendency to renewables is one of the consequences of changing attitudes towards energy issues. As a result, solar energy, which is the leader among renewable energies based on availability and potential, plays a crucial role in full filing global needs. Significant problems with the solar thermal power plants (STPP) are the operation time, which is limited by daylight and is approximately half of the power plants with fossil fuels, and the capital cost. Exergy analysis survey of STPP hybrid with PCM storage carried out using Engineering Equation Solver (EES) program with genetic algorithm (GA) for three different scenarios, based on eight decision variables, which led us to decrease final product cost (electricity) in optimized scenario up to 30% compare to base case scenario from 28.99 $/kWh to 20.27 $/kWh for the case study. Also, in the optimal third scenario of this plant, the inner carbon dioxide gas cycle produces 1200 kW power with a thermal efficiency of 59% and also 1000 m3/h water with an exergy efficiency of 23.4% and 79.70 kg/h with an overall exergy efficiency of 34% is produced in the tetrageneration plant.

Multi-objective path planning for mobile robot in nuclear accident environment based on improved ant colony optimization with modified A*

  • De Zhang;Run Luo;Ye-bo Yin;Shu-liang Zou
    • Nuclear Engineering and Technology
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    • 제55권5호
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    • pp.1838-1854
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    • 2023
  • This paper presents a hybrid algorithm to solve the multi-objective path planning (MOPP) problem for mobile robots in a static nuclear accident environment. The proposed algorithm mimics a real nuclear accident site by modeling the environment with a two-layer cost grid map based on geometric modeling and Monte Carlo calculations. The proposed algorithm consists of two steps. The first step optimizes a path by the hybridization of improved ant colony optimization algorithm-modified A* (IACO-A*) that minimizes path length, cumulative radiation dose and energy consumption. The second module is the high radiation dose rate avoidance strategy integrated with the IACO-A* algorithm, which will work when the mobile robots sense the lethal radiation dose rate, avoiding radioactive sources with high dose levels. Simulations have been performed under environments of different complexity to evaluate the efficiency of the proposed algorithm, and the results show that IACO-A* has better path quality than ACO and IACO. In addition, a study comparing the proposed IACO-A* algorithm and recent path planning (PP) methods in three scenarios has been performed. The simulation results show that the proposed IACO-A* IACO-A* algorithm is obviously superior in terms of stability and minimization the total cost of MOPP.

OPR1000 발전소의 핵연료 주기비분석을 통한 최적 배취 크기와 핵연료 농축도 결정 (Determination of Optimum Batch Size and Fuel Enrichment for OPR1000 NPP Based on Nuclear Fuel Cycle Cost Analysis)

  • 조성주;하창주
    • 에너지공학
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    • 제23권4호
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    • pp.256-262
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    • 2014
  • 국내 원자력발전소의 주기길이는 전력회사의 전력수급계획에 따라 결정된다. 주기길이는 노심에 장전할 신연료 다발수와 핵연료 농축도를 조정하여 결정할 수 있다. 전력회사에서는 특정 주기길이를 만족시키기 위한 방법으로 신연료 다발수를 정한 후 핵연료 농축도를 결정하는 방법을 적용하고 있다. 그러나 이 방법의 경우 같은 주기길이를 갖는 다른 신연료 다발수와 핵연료 농축도의 조합들 보다 핵연료 주기비 측면에서 가장 경제적인지 판단할 수가 없다. 따라서 본 분석에서는 상용 노심설계 코드인 CASMO/MASTER 코드를 사용하여 OPR1000(Optimized Power Reactor 1000) 발전소를 대상으로 신연료 다발수와 핵연료 농축도 조합에 대한 노심 연소계산을 수행하여 동일한 주기길이를 갖는 최적의 신연료 다발수와 핵연료 농축도 조합은 무엇인지 분석하였다. 천이노심계산에서 발생할 수 있는 불확실도를 최소화하기 위해 노심 특성인자들이 변하지 않는 평형노심(equilibrium cycle)까지 계산을 수행하여 이때의 계산결과를 핵연료 주기비 계산에 사용하였다. 또한 평준화 핵연료 주기비(levelized fuel cycle cost) 계산에 있어 중요한 인자인 할인율(discount rate)에 대해서 국내뿐만 아니라 다른 나라의 실정에도 적용 가능하도록 민감도 분석을 수행하였다. 평준화 핵연료 주기비(levelized fuel cycle cost) 평가 결과 할인율(discount rate)이 낮은 경우 신연료 다발수는 줄이고 대신 핵연료 농축도를 높이는 조합을 통해 특정 주기길이를 만족시키는 방법이 경제적인 것으로 나타났다. 반면 할인율(discount rate)이 높은 경우는 핵연료 농축도는 낮추고 신연료 다발수를 늘리는 조합을 통해 특정 주기길이를 만족시키는 방법이 경제적인 것으로 나타났다.