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Davide Pizzocri
Davide Pizzocri
Politecnico di Milano
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An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions
KA Gamble, T Barani, D Pizzocri, JD Hales, KA Terrani, G Pastore
Journal of nuclear materials 491, 55-66, 2017
1322017
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS
T Barani, E Bruschi, D Pizzocri, G Pastore, P Van Uffelen, RL Williamson, ...
Journal of Nuclear Materials 486, 96-110, 2017
712017
SCIANTIX: a new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes
D Pizzocri, T Barani, L Luzzi
Journal of Nuclear Materials 532, 152042, 2020
682020
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools
D Pizzocri, G Pastore, T Barani, A Magni, L Luzzi, P Van Uffelen, SA Pitts, ...
Journal of Nuclear Materials 502, 323-330, 2018
562018
Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels
F Cappia, D Pizzocri, A Schubert, P Van Uffelen, G Paperini, D Pellottiero, ...
Journal of Nuclear Materials 480, 138-149, 2016
522016
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions
T Barani, G Pastore, D Pizzocri, DA Andersson, C Matthews, A Alfonsi, ...
Journal of Nuclear Materials 522, 97-110, 2019
472019
Properties of the high burnup structure in nuclear light water reactor fuel
T Wiss, VV Rondinella, RJM Konings, D Staicu, D Papaioannou, ...
Radiochimica Acta 105 (11), 893-906, 2017
462017
Microhardness and Young's modulus of high burn-up UO2 fuel
F Cappia, D Pizzocri, M Marchetti, A Schubert, P Van Uffelen, L Luzzi, ...
Journal of Nuclear Materials 479, 447-454, 2016
452016
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor
L Luzzi, A Cammi, V Di Marcello, S Lorenzi, D Pizzocri, P Van Uffelen
Nuclear Engineering and Design 277, 173-187, 2014
442014
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution
G Pastore, D Pizzocri, C Rabiti, T Barani, P Van Uffelen, L Luzzi
Journal of Nuclear Materials 509, 687-699, 2018
412018
Modelling of transient fission gas behaviour in oxide fuel and application to the BISON code
G Pastore, D Pizzocri, JD Hales, SR Novascone, DM Perez, BW Spencer, ...
Enlarged Halden Programme Group Meeting, Røros, Norway, 2014
402014
PolyPole-1: an accurate numerical algorithm for intra-granular fission gas release
D Pizzocri, C Rabiti, L Luzzi, T Barani, P Van Uffelen, G Pastore
Journal of Nuclear Materials 478, 333-342, 2016
342016
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant
L Cognini, D Pizzocri, T Barani, P Van Uffelen, A Schubert, T Wiss, L Luzzi
Nuclear Engineering and Design 340, 240-244, 2018
322018
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations
L Luzzi, L Cognini, D Pizzocri, T Barani, G Pastore, A Schubert, T Wiss, ...
Nuclear Engineering and Design 330, 265-271, 2018
302018
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation
T Barani, D Pizzocri, F Cappia, L Luzzi, G Pastore, P Van Uffelen
Journal of Nuclear Materials 539, 152296, 2020
292020
A semi-empirical model for the formation and depletion of the high burnup structure in UO2
D Pizzocri, F Cappia, L Luzzi, G Pastore, VV Rondinella, P Van Uffelen
Journal of Nuclear Materials 487, 23-29, 2017
292017
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications
A Magni, T Barani, A Del Nevo, D Pizzocri, D Staicu, P Van Uffelen, ...
Journal of Nuclear Materials 541, 152410, 2020
262020
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients
T Barani, G Pastore, A Magni, D Pizzocri, P Van Uffelen, L Luzzi
Journal of Nuclear Materials 538, 152195, 2020
242020
Isotropic softening model for fuel cracking in BISON
T Barani, D Pizzocri, G Pastore, L Luzzi, JD Hales
Nuclear Engineering and Design 342, 257-263, 2019
242019
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR
L Luzzi, S Lorenzi, D Pizzocri, D Rozzia, A Aly, A Del Nevo
Report RdS/PAR2013/022, 2014
232014
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