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
- 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
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COMPUTER CODES
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D CODES
DATA COVARIANCES
E CODES
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NEUTRON TRANSPORT THEORY
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NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
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OPERATION
PERTURBATION THEORY
PHYSICS
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REACTIVITY
REACTOR COMPONENTS
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TRANSPORT THEORY
US AEC
US DOE
US ERDA
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