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

* Corresponding author
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.
Keywords :
Document type :
Conference papers
Domain :

Cited literature [13 references]

https://hal-cea.archives-ouvertes.fr/cea-02442369
Contributor : Amplexor Amplexor <>
Submitted on : Thursday, January 16, 2020 - 1:43:45 PM
Last modification on : Monday, July 27, 2020 - 12:56:03 PM
Long-term archiving on: : Friday, April 17, 2020 - 8:08:26 PM

### File

201600000274.pdf
Files produced by the author(s)

### Identifiers

• HAL Id : cea-02442369, version 1

### Citation

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⟩

Record views