• Title/Summary/Keyword: Nuclear Fuel Cycle

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NUCLEAR FUEL CYCLE COST ESTIMATION AND SENSITIVITY ANALYSIS OF UNIT COSTS ON THE BASIS OF AN EQUILIBRIUM MODEL

  • KIM, S.K.;KO, W.I.;YOUN, S.R.;GAO, R.X.
    • Nuclear Engineering and Technology
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    • v.47 no.3
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    • pp.306-314
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    • 2015

  • This paper examines the difference in the value of the nuclear fuel cycle cost calculated by the deterministic and probabilistic methods on the basis of an equilibrium model. Calculating using the deterministic method, the direct disposal cost and Pyro-SFR (sodium-cooled fast reactor) nuclear fuel cycle cost, including the reactor cost, were found to be 66.41 mills/kWh and 77.82 mills/kWh, respectively (1 mill = one thousand of a dollar, i.e., $10^{-3}$ $). This is because the cost of SFR is considerably expensive. Calculating again using the probabilistic method, however, the direct disposal cost and Pyro-SFR nuclear fuel cycle cost, excluding the reactor cost, were found be 7.47 mills/kWh and 6.40 mills/kWh, respectively, on the basis of the most likely value. This is because the nuclear fuel cycle cost is significantly affected by the standard deviation and the mean of the unit cost that includes uncertainty. Thus, it is judged that not only the deterministic method, but also the probabilistic method, would also be necessary to evaluate the nuclear fuel cycle cost. By analyzing the sensitivity of the unit cost in each phase of the nuclear fuel cycle, it was found that the uranium unit price is the most influential factor in determining nuclear fuel cycle costs.

  • https://doi.org/10.1016/j.net.2014.12.018 인용 KSCI

TSPA 2006 and Its Implication

  • Hwang, Y.;Kang, C.H.;Lee, Y.M.;Jeong, M.S.;Lee, S.H.
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2007.05a
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    • pp.105-106
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    • 2007

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DEVELOPMENT AND VALIDATION OF A NUCLEAR FUEL CYCLE ANALYSIS TOOL: A FUTURE CODE

  • Kim, S.K.;Ko, W.I.;Lee, Yoon Hee
    • Nuclear Engineering and Technology
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    • v.45 no.5
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    • pp.665-674
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    • 2013

  • This paper presents the development and validation methods of the FUTURE (FUel cycle analysis Tool for nUcleaR Energy) code, which was developed for a dynamic material flow evaluation and economic analysis of the nuclear fuel cycle. This code enables an evaluation of a nuclear material flow and its economy for diverse nuclear fuel cycles based on a predictable scenario. The most notable virtue of this FUTURE code, which was developed using C# and MICROSOFT SQL DBMS, is that a program user can design a nuclear fuel cycle process easily using a standard process on the canvas screen through a drag-and-drop method. From the user's point of view, this code is very easy to use thanks to its high flexibility. In addition, the new code also enables the maintenance of data integrity by constructing a database environment of the results of the nuclear fuel cycle analyses.

  • https://doi.org/10.5516/NET.06.2012.081 인용 PDF KSCI KPUBS

Safety Analyses of Process and Facility for the ACP Demonstration

  • You, Gil-Sung;Choung, Won-Myung;Ku, Jeong-Hoe;Cho, Il-Je;Kook, Dong-Hak;Lee, Eun-Pyo;Park, Seong-Won
    • Proceedings of the Korean Nuclear Society Conference
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    • 2005.05a
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    • pp.293-294
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    • 2005

  • The safety analyses and evaluation works on the process and facility for ACP demonstration have been performed. The several safety factors, such as the risk, environmental, radiation, structural, criticality, were analyzed. The analysis results confirmed the reliability of the safety on the ACP process and facility during normal and accident conditions.

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