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Economic analysis of complex nuclear fuel cycles with NE-COST

  • Francesco Ganda
  • , Brent Dixon
  • , Edward Hoffman
  • , Taek K. Kim
  • , Temitope Taiwo
  • , Roald Wigeland

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

The purpose of this work is to present a new methodology, and associated computational tools, developed within the U.S. Department of Energy Fuel Cycle Option Campaign to quantify the economic performance of complex nuclear fuel cycles. The levelized electricity cost at the busbar is generally chosen to quantify and compare the economic performance of different baseload generating technologies, including of nuclear: it is the cost of electricity which renders the risk-adjusted discounted net present value of the investment cash flow equal to zero. The work presented here is focused on the calculation of the levelized cost of electricity of fuel cycles at mass balance equilibrium, which is termed LCAE (Levelized Cost of Electricity at Equilibrium). To alleviate the computational issues associated with the calculation of the LCAE for complex fuel cycles, a novel approach has been developed, which has been called the "island approach " because of its logical structure: a generic complex fuel cycle is subdivided into subsets of fuel cycle facilities, called islands, each containing one and only one type of reactor or blanket and an arbitrary number of fuel cycle facilities. A nuclear economic software tool, NE-COST, written in the commercial programming software MATLAB®, has been developed to calculate the LCAE of complex fuel cycles with the "island" computational approach. NE-COST has also been developed with the capability to handle uncertainty: the input parameters (both unit costs and fuel cycle characteristics) can have uncertainty distributions associated with them, and the output can be computed in terms of probability density functions of the LCAE. In this paper NE-COST will be used to quantify, as examples, the economic performance of (1) current LWR once-through systems; (2) continuous Pu recycling in fast reactors with driver and blanket (FR); (3) Recycling of Pu bred in FR into LWR. For each fuel cycle, the contributions to the total LCAE of the main cost components will be identified.

Original languageEnglish
Title of host publicationInternational Congress on Advances in Nuclear Power Plants, ICAPP 2014
PublisherAmerican Nuclear Society
Pages2073-2085
Number of pages13
ISBN (Print)9781632668264
StatePublished - 2014
EventInternational Congress on Advances in Nuclear Power Plants, ICAPP 2014 - Charlotte, NC, United States
Duration: Apr 6 2014 → Apr 9 2014

Publication series

NameInternational Congress on Advances in Nuclear Power Plants, ICAPP 2014
Volume3

Conference

ConferenceInternational Congress on Advances in Nuclear Power Plants, ICAPP 2014
Country/TerritoryUnited States
CityCharlotte, NC
Period04/6/14 → 04/9/14

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