Paolo Balestra
Paolo Balestra
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Cited by
New RELAP5-3D lead and LBE thermophysical properties implementation for safety analysis of Gen IV reactors
P Balestra, F Giannetti, G Caruso, A Alfonsi
Science and Technology of Nuclear Installations 2016, 2016
Pronghorn: A Multidimensional Coarse-Mesh Application for Advanced Reactor Thermal Hydraulics
AJ Novak, RW Carlsen, S Schunert, P Balestra, D Reger, RN Slaybaugh, ...
Nuclear Technology, 1-32, 2021
Improvements to PHISICS/RELAP5-3D© Capabilities for Simulating HTGRs
P Balestra, A Alfonsi, G Strydom, C Rabiti, F Giannetti, G Caruso
Transaction of American Nuclear Society 116 (1), 1009-1012, 2017
Simulation of AER-DYN-002 and AER-DYN-003 Control Rod Ejection Benchmarks by RELAP5-3D/PHISICS Coupled Codes
P Balestra, C Parisi, A Alfonsi, C Rabiti
Nuclear Technology 193 (1), 175-182, 2016
Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application
Y Wang, S Schunert, J Ortensi, V Laboure, M DeHart, Z Prince, F Kong, ...
Nuclear Technology, 1-26, 2021
PBMR-400 Benchmark Solution of Exercise 1 and 2 Using the MOOSE Based Applications: MAMMOTH, Pronghorn
P Balestra, S Schunert, RW Carlsen, AJ Novak, MD DeHart, ...
EPJ Web of Conferences 247, 06020, 2021
Modelling and Simulation of a Liquid Fuel Molten Salt Reactor Core Using Gen-Foam
S Bhaskar, M Altahhan, D Ziyad, P Balestra, J Hou, M Avramova, N Smith
4th Int. Conf. Physics and Technology of Reactors and Applications (PHYTRA4 …, 2018
IAEA Neutronics Benchmark for EBR-II SHRT-45R
B Vezzoni, M Marchetti, WFG van Rooijen, T Fei, Y Zhang, P Balestra, ...
Integral study of accident sequences with reference to NPPs next to the Italian borders
F Mascari
ENEA, 2015
Development and validation of an approach and numerical models for safety analysis of FBR
P Console Camprini, C Parisi, I Di Piazza, A Del Nevo
ENEA, 2014
New PHISICS Perturbation Method Module Verification Using the HTTR Neutronic Model
P Balestra, A Alfonsi, G Strydom, RS Sen, C Rabiti, F Giannetti, G Caruso
Transaction of American Nuclear Society 116 (1), 1009-1012, 2017
NRC Multiphysics Analysis Capability Deployment FY2021-Part 1
S Schunert, P Balestra, GL Giudicelli, R Freile, L Harbour, J Ortensi
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020
Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam
MR Altahhan, S Bhaskar, D Ziyad, P Balestra, C Fiorina, J Hou, N Smith, ...
Nuclear Engineering and Design 369, 110826, 2020
3D Coupled Transient simulation of a fast liquid fuel molten salt reactor primary loop using GeN-Foam
M Altahhan, S Bhaskar, P Balestra, J Hou, M Avramova, N Smith, ...
Proc. NURETH 18, 18-23, 2019
Advanced Liquid Fuel Molten Salt Reactor Core Simulation Using Gen-Foam
M Altahhan, S Bhaskar, P Balestra, J Hou, M Avramova, N Smith
Advances in Thermal Hydraulics (ATH 2018), Orlando, Florida, 2018
Single and two-phase sodium flow analysis for two TUCOP CABRI tests using the ASTEC-Na code
S Perez-Martin, W Pfrang, G Bandini, S Ederli, P Balestra, C Parisi
Proc. of 16th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics …, 2015
Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor
AJ Novak, S Schunert, RW Carlsen, P Balestra, RN Slaybaugh, ...
Annals of Nuclear Energy 154, 107968, 2021
Modular high temperature gas reactor core modeling with RELAP5-3D/PHISICS–Optimization schemes for load following
P Balestra, K Henry, C Carlyon, C English, J Myer, M Avramova, A Epiney, ...
Nuclear Engineering and Design 362, 110526, 2020
Modular HIGH Temperature Gas Reactor Core Modeling with RELAP5-3D/PHISICS–Optimization Schemes for Load Following
K Henry, C Carlyon, C English, J Myer, P Balestra, M Avramova, A Epiney, ...
HTR 2018, 2018
Pre-test analyses for the experimental sodium loop KASOLA with ASTEC-Na and benchmarking with other codes
G Bandini, S Ederli, C Parisi, P Balestra, M Haselbauer, S Perez-Martin, ...
Proc. of International Congress on Advances in Nuclear Power Plants (ICAPP …, 2015
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