Old Web
English
Sign In
Acemap
>
authorDetail
>
Laurence San Felice
Laurence San Felice
Burnup
Nuclear engineering
Post Irradiation Examination
Fission products
Actinide
3
Papers
3
Citations
0
KQI
Citation Trend
Filter By
Interval:
1900~2024
1900
2024
Author
Papers (3)
Sort By
Default
Most Recent
Most Early
Most Citation
No data
Journal
Conference
Others
MOx Depletion Calculation Benchmark
2016
Laurence San Felice
Romain Eschbach
Ratna Dewi Syarifah
Seif-Eddine Maryam
Kevin Hesketh
Show All
Source
Cite
Save
Citations (1)
First burnup credit application including actinides and fission products for transport and storage cask by using French experiments
2015
Journal of Nuclear Science and Technology
Marcel Tardy
Stavros Kitsos
Gabriele Grassi
Alain Santamarina
Laurence San Felice
Cécile Riffard
Show All
Source
Cite
Save
Citations (2)
Improvement of the experimental validation of the DARWIN code system due to the JEFF3.1 library for UOX spent fuel inventory and decay heat calculation - synthesis of the tendencies obtained with the MALIBU international benchmark and the French Post-Irradiation Examination database
2008
Romain Eschbach
Cécile Riffard
Laurence San Felice
Pierre Marimbeau
Christophe Venard
Frédéric Laugier
Jean-François Thro
Show All
Source
Cite
Save
Citations (0)
1