• Title/Summary/Keyword: Cask

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DEVELOPMENT OF A COMPUTER PROGRAM FOR AN ANALYSIS OF THE LOGISTICS AND TRANSPORTATION COSTS OF THE PWR SPENT FUELS IN KOREA

  • Cha, Jeong-Hun;Choi, Heui-Joo;Lee, Jong-Youl;Choi, Jong-Won
    • Journal of Radiation Protection and Research
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    • v.34 no.1
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    • pp.1-7
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    • 2009

  • It is expected that a substantial amount of spent fuels will be transported from the four nuclear power plant (NPP) sites in Korea to a hypothetical centralized interim storage facility or a final repository in the near future. The cost for the transportation is proportional to the amount of spent fuels. In this paper, a cost estimation program is developed based on the conceptual design of a transportation system and a logistics analysis. Using the developed computer program, named as CASK, the minimum capacity of a centralized interim storage facility (CISF) and the transportation cost for PWR spent fuels are calculated. The PWR spent fuels are transported from 4 NPP sites to a final repository (FR) via the CISF. Since NPP sites and the CISF are located along the coast, a sea-transportation is considered and a road-transportation is considered between the CISF and the FR. The result shows that the minimum capacity of the interim storage facility is 15,000 MTU.

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On using computational versus data-driven methods for uncertainty propagation of isotopic uncertainties

  • Radaideh, Majdi I.;Price, Dean;Kozlowski, Tomasz
    • Nuclear Engineering and Technology
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    • v.52 no.6
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    • pp.1148-1155
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    • 2020

  • This work presents two different methods for quantifying and propagating the uncertainty associated with fuel composition at end of life for cask criticality calculations. The first approach, the computational approach uses parametric uncertainty including those associated with nuclear data, fuel geometry, material composition, and plant operation to perform forward depletion on Monte-Carlo sampled inputs. These uncertainties are based on experimental and prior experience in criticality safety. The second approach, the data-driven approach relies on using radiochemcial assay data to derive code bias information. The code bias data is used to perturb the isotopic inventory in the data-driven approach. For both approaches, the uncertainty in keff for the cask is propagated by performing forward criticality calculations on sampled inputs using the distributions obtained from each approach. It is found that the data driven approach yielded a higher uncertainty than the computational approach by about 500 pcm. An exploration is also done to see if considering correlation between isotopes at end of life affects keff uncertainty, and the results demonstrate an effect of about 100 pcm.

  • https://doi.org/10.1016/j.net.2019.11.029 인용 PDF KSCI