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

(1) , (1) , (1) , (1) , (1)
1

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.
Fichier principal
Vignette du fichier
201600000274.pdf (162.87 Ko) Télécharger le fichier
Origin : Files produced by the author(s)
Loading...

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⟩

Collections

CEA DEN
17 View
26 Download

Share

Gmail Facebook Twitter LinkedIn More