, Spent fuel, 2011.
Experimental validation of the DARWIN2.3 package for fuel cycle applications, Nuclear Technol, vol.184, p.217, 2013. ,
3: An industrial tool for nuclear fuel and waste characterization with associated qualification, Proc. Int. Conf. WM, 2012. ,
, Nucl. Eng. Tech, vol.42, p.474, 2010.
DARWIN: an evolution code system for a large range of applications, J. Nuclear Sci. Technol, vol.1, p.845, 2000. ,
The JEFF-3.1.1 nuclear data library, JEFF Report, vol.22, 2009. ,
The SHEM energy mesh for accurate fuel depletion and BUC calculations, Proc. Int. Conf. Nuclear Criticality-Safety ICNC2007, 2007. ,
APOLLO2: test of recently implemented methods applied to the calculation of a large scale heterogeneous cluster, Proc. Int. Conf. PHYSOR 2002, 2002. ,
New modeling of LWR assemblies using the APOLLO2 code package, Proc. Joint Int. Topl. Mtg. Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA 2007), 2007. ,
, Predictive science academic alliance -Program-II (PSAAP-II) -Verification, Validation, and Uncertainty Quantification -Whitepaper (U), LLNL-MI-481471, 2011.
Verification, validation, and predictive capability in computational engineering and physics, Appl. Mech. Rev, vol.57, p.345, 2004. ,
Verification, validation and uncertainty quatification in multi-physics modeling for nuclear reactor design and safety analysis, Prog. Nuclear Energy, vol.52, p.602, 2010. ,
Verification, validation and uncertainty quantification for neutronic calculation for ASTRID fast reactor detailed design, Proc. Int. Conf. PHYSOR 2016 Sun, 2016. ,
Systematic uncertainty due to statistics in Monte Carlo burnup codes: applications to a simple benchmark with TRIPOLI-4-D, Prog. Nuclear Sci. Technol, vol.2, p.879, 2011. ,
First verification and validation steps of MENDEL release V1.0 cycle code system, Proc. Int. Conf. PHYSOR2014, 2014. ,
Work plan for improving the DARWIN2.3 depleted material balance calculation concerning some important isotopes for fuel cycle, Proc. Int. Conf. Nuclear Data for Science and Technology, 2016. ,
Validation of the uncertainty propagation method for the decay heat within the DARWIN2.3 package, Proc. ANS Best Estimate Plus Uncertainty Int. Conf. (BEPU 2018), 2018. ,
Comparison of deterministic and stochastic approaches for isotopic concentration and decay heat uncertainty quantification on elementary fission pulse, EPJ Web Conf, vol.11, p.9002, 2016. ,
COMAC: Nuclear Data Covariance Matrices Library for Reactor Applications, Proc. Int. Conf. PHYSOR 2014, 2014. ,
URANIE: The CEA/DEN uncertainty and sensitivity platform, Procedia-Soc. Behavioral Sci, vol.2, p.7660, 2010. ,
Validation of the uncertainty propagation method for the decay heat within the DARWIN2.3 package, Proc. Int. Conf. Best Estimate Plus Uncertainty (BEPU 2018), 2018. ,
Application of the bias transposition method on PWR decay heat calculations with the DARWIN2.3 package, Proc. Int. Conf. GLOBAL2017, 2017. ,
, EPJ Nuclear Sci. Technol, vol.5, p.9, 2019.
Improved Fission product yield evaluation methodologies, WPEC Subgroup Proposal, 2012. ,
A Bayesian Monte Carlo method for fission yield covariance information, Ann. Nuclear Energy, vol.95, p.125, 2016. ,
Covariance Evaluation for Nuclear Data of Interest to the Reactivity Loss Estimation of the Jules Horowitz Material Testing Reactor, 2016. ,
French) 27. International standard, Énergie nucléaire -Réacteurs à eau légère -Calcul de la puissance résiduelle des combustibles nucléaires, JEFF3 et les calculs de puissance résiduelle, 2009. ,
Measurements of Gamma-Ray Decay Heat of Fission Products for Fast Neutron Fission of 235 U, 239 Pu and 233 U, J. Atom. Energ. Soc. Jpn, vol.24, p.709, 1982. ,
Measurement of Fission-product Decay Heat for Fast Reactors, Proc. Int. Conf. Nuclear Data for Science and Technology, vol.237, 1982. ,
Fission-product energy release for times following thermal-neutron Fission 239, 241 Pu between 2 and 14000 s, Nucl. Sci. Eng, vol.78, p.126, 1981. ,
Fission-product energy release for times following thermal-neutron fission 235 U between 2 and 14000 s, Nucl. Sci. Eng, vol.74, p.106, 1980. ,
Analysis of MERCI decay heat measurement for PWR UO2 fuel rod, Nuclear Technol, vol.177, p.73, 2012. ,
Measurements of decay heat in spent nuclear fuel at the Swedish interim storage facility CLAB, Svensk Kärnbränslehantering AB, 2006. ,
Problems of Fast Reactor Physics related to breeding, At. Energy Rev, vol.18, p.4, 1980. ,
Optimisation de l'approche de représenta-tivité et de transposition pour la conception neutronique de programmes expérimentaux dans les maquettes critiques, 2013. ,
A global approach of the representativity concept, Application on a highconversion light water reactor MOX lattice case, Proc. Int ,
, Conf. Mathematics and Computational Methods Applied to Nuclear Science & Engineering, 2013.
The similarity/transposition theory to assess accurately MOX 15 × 15 used fuel inventory with DAR-WIN2.3, Proc. Int. Conf. GLOBAL2017, Seoul, 2017. ,
Incertitude sur la puissance résiduelle due aux incertitudes sur les données de produits de fission, 1996. ,
Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel, Oak Ridge National Laboratory, NUREG/CR-6972, 2010. ,
Experimental Validation of Decay Heat Calculations with VESTA 2.1, Proc. Int. Conf. PHYSOR 2014, 2014. ,
In-plant test measurements for spent fuel storage at morris operation, Fuel bundle heat generation rates, vol.3, 1982. ,
ORIGEN2 Calculations of PWR Spent Fuel Decay Heat Compared with Calorimeter Data, 1984. ,
Puissance residuelle totale emise par les produits de fission thermique de l' 235 U, J. Nucl. Energy, vol.27, p.597, 1973. ,
Gamma-ray spectra and decay heat following 235 U thermal neutron fission, 1997. ,
Mesures calorimetriques de la puissance residuelle totale emise par les produits de fission thermique de 233 U et 239 Pu, Centre d'Études Nucleaires de Cadarache, 1976. ,
Integral determination of the Beta and Gamma heat in thermal-neutron-induced Fission of ,
, Proc
Nuclear Data for Science and Technology, 1987. ,
Decay heat measurements following neutron fission of 235 U and 239 Pu, Proc. Int. Conf. Nuclear Data for Science and Technology, 1997. ,
Feasibility of decay heat uncertainty reduction using nuclear data adjustment method with experimental data, J. Nuclear Sci. Technol, vol.54, p.213, 2017. ,
How to obtain an enhanced extended uncertainty associated with decay heat calculations of industrial PWRs using the DARWIN2.3 package, EPJ Nuclear Sci. Technol, vol.5, 2019. ,