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The impact of ENDF/B-V fission spectrum parameter uncertainty on the prediction of fast reactor burnup performance

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:7090484
; ;  [1]
  1. Purdue Univ., Lafayette, IN (United States)
The sensitivity and uncertainty of various core burnup performance quantities (e.g., k[sub eff], burnup reactivity swing, local power density, etc.) to the heavy isotope fission spectrum parameters was investigated using depletion perturbation methods and ENDF/B-V covariance data. A brief description of the methods is followed by results of a 900-MW(thermal) fast reactor. The analysis here indicates that for a 900-MW(thermal) heterogeneous fast reactor, the experimental error in the ENDF/B-V fission spectrum parameters does not have a major impact on calculational uncertainty in the core burnup performance.
OSTI ID:
7090484
Report Number(s):
CONF-901101--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
Country of Publication:
United States
Language:
English