Uncertainty quantification of delayed neutron fraction of u235 based fuel cores - Archive ouverte HAL Access content directly
Conference Papers Year : 2016

## Uncertainty quantification of delayed neutron fraction of u235 based fuel cores

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1
G. Rimpault

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#### Abstract

The analysis of nuclear reactors behavior in transients depends among others on the effective delayed neutron fraction ($\beta _{eff}$). The present paper aims at describing how to provide uncertainties for the effective delayed neutron fraction ($\beta_{eff}$) to be used for safety studies.The use of the Iterated Fission Probability method in the Monte Carlo code TRIPOLI4 gives credit to deterministic codes such as ERANOS for calculating $\beta _{eff}$. The use of the Monte Carlo code TRIPOLI4 enables a better representation of experimental cores, especially the R2 experimental core which exhibit more heterogeneities for hosting experimental devices. Its use for evaluating the calculated parts of the $\beta _{eff}$ has been found essential. The nuclear data uncertainty propagation has been leading to a 3.5% uncertainty. This 3.5% uncertainty is confirmed by the $\beta _{eff}$ C-E bias for BERENICE R2 cores.

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### Dates and versions

cea-02442369 , version 1 (16-01-2020)

### Identifiers

• HAL Id : cea-02442369 , version 1

### Cite

D. Blanchet, G. Rimpault, P. Dufay, J. Tommasi, G. Truchet. Uncertainty quantification of delayed neutron fraction of u235 based fuel cores. PHYSOR 2016 - The Physics of Reactors conferences: Unifying Theory and Experiments in the 21st Century, May 2016, Sun Valley, United States. ⟨cea-02442369⟩

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