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Title: Application of sensitivity analysis in DYMOND/Dakota to fuel cycle transition scenarios

Journal Article · · EPJ Nuclear Sciences and Technologies
DOI:https://doi.org/10.1051/epjn/2021024· OSTI ID:1841572
 [1];  [1]
  1. Argonne National Lab. (ANL), Lemont, IL (United States)

The ability to perform sensitivity analysis has been enabled for the nuclear fuel cycle simulator DYMOND through its coupling with the design and analysis toolkit Dakota. To test and demonstrate these new capabilities, a transition scenario and multi-parameter study were devised. The transition scenario represents a partial transition from the US nuclear fleet to a closed fuel cycle with small modular LWRs and fast reactors fueled by reprocessed used nuclear fuel. Four uncertain parameters in this transition were studied – start date of reprocessing, total reprocessing capacity, the nuclear energy demand growth, and the rate at which the fast reactors are deployed – with respect to their impact on four response metrics. The responses – total natural uranium consumed, maximum annual enrichment capacity required, total disposed mass, and total cost of the nuclear fuel cycle – were chosen based on measures known to be of interest in transition scenarios and to be significantly impacted by the varying parameters. Furthermore, analysis of this study was performed both from the direct sampling and through surrogate models developed in Dakota to calculate the global sensitivity measures Sobol’ indices. This example application of this new capability showed that the most consequential parameter to most metrics was the share of new build capacity that is fast reactors. However, for the cost metric, the scaling factor of the energy demand growth was significant and had synergistic behavior with the fast reactor new build share.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC02-06CH11357
OSTI ID:
1841572
Journal Information:
EPJ Nuclear Sciences and Technologies, Vol. 7; ISSN 2491-9292
Publisher:
EDP SciencesCopyright Statement
Country of Publication:
United States
Language:
English

References (3)

NuScale small modular reactor for Co-generation of electricity and water journal May 2014
A methodology for performing sensitivity analysis in dynamic fuel cycle simulation studies applied to a PWR fleet simulated with the CLASS tool journal January 2018
Core design studies for a 1000MWth Advanced Burner Reactor journal April 2009

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