| Nome |
# |
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Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum, file e384c42f-10dd-d4b2-e053-9f05fe0a1d67
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188
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Radiative heat load distribution on the EU-DEMO first wall due to mitigated disruptions, file e384c432-d5e6-d4b2-e053-9f05fe0a1d67
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58
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Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors, file e384c431-fb78-d4b2-e053-9f05fe0a1d67
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48
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A methodology for the identification of the postulated initiating events of the Molten Salt Fast Reactor, file e384c430-eb89-d4b2-e053-9f05fe0a1d67
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47
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STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION, file e384c432-67e0-d4b2-e053-9f05fe0a1d67
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33
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Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects, file e384c430-b91f-d4b2-e053-9f05fe0a1d67
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31
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Application of the lines of defence method to the molten salt fast reactor in the framework of the SAMOFAR project, file e384c431-5236-d4b2-e053-9f05fe0a1d67
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31
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Preliminary uncertainty and sensitivity analysis of the Molten Salt Fast Reactor steady-state using a Polynomial Chaos Expansion method, file e384c433-5cb7-d4b2-e053-9f05fe0a1d67
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27
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Coupled modelling of the EBR-II SHRT-45R including photon heat deposition, file e384c432-3398-d4b2-e053-9f05fe0a1d67
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23
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Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient, file e384c432-fb61-d4b2-e053-9f05fe0a1d67
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21
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Analysis of KUCA measurements by the reactivity monitoring MAρTA method, file e384c433-1376-d4b2-e053-9f05fe0a1d67
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15
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Uncertainty quantification in steady state simulations of a molten salt system using polynomial chaos expansion analysis, file e384c432-4591-d4b2-e053-9f05fe0a1d67
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14
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A method for the continuous monitoring of reactivity in subcritical source-driven systems, file e384c433-2291-d4b2-e053-9f05fe0a1d67
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13
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New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method, file e384c433-1aeb-d4b2-e053-9f05fe0a1d67
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10
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A non-intrusive reduced order model for light water reactor core stability analysis, file e384c434-ba9d-d4b2-e053-9f05fe0a1d67
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9
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Erratum: “Radiative heat load distribution on the EU-DEMO first wall due to mitigated disruptions” (Nuclear Materials and Energy (2020) 25, (S2352179120300971), (10.1016/j.nme.2020.100824)), file e384c434-bd65-d4b2-e053-9f05fe0a1d67
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9
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PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS, file e384c432-c3fb-d4b2-e053-9f05fe0a1d67
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8
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Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications, file af06dd72-942e-4d22-b47e-848bb757e932
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7
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Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem, file 390249dd-4b6e-48db-b17f-820bfe738c98
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6
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Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis, file 6f9f7fc4-2e5e-467a-ba78-8135016fb45d
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6
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Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code, file e384c434-8e3a-d4b2-e053-9f05fe0a1d67
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6
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A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor, file 95fcbc20-560b-4cfa-beef-1860883e4712
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5
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PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS, file e384c42e-817c-d4b2-e053-9f05fe0a1d67
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5
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Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed, file e384c430-48f6-d4b2-e053-9f05fe0a1d67
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5
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Monte Carlo modelling of the ARC Breeding Blanket with the Serpent code , file 12692cad-26c9-4a3a-8808-0f13e6d189a2
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4
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A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor, file 230f3ca9-5ab5-4b1e-82c6-ea3353e511cc
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4
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Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis, file 482b8abe-02e9-4ed0-9643-7956ba43c784
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4
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Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors, file 8e25a240-307f-4808-8335-7022d7ed5fef
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4
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null, file e285d67b-1bc8-4043-80d1-099e98143758
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4
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A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors, file e384c42e-269f-d4b2-e053-9f05fe0a1d67
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4
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PRELIMINARY FUNCTIONAL SAFETY ASSESSMENT FOR MOLTEN SALT FAST REACTORS IN THE FRAMEWORK OF THE SAMOFAR PROJECT, file e384c42f-dca1-d4b2-e053-9f05fe0a1d67
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4
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Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient, file e384c42f-e869-d4b2-e053-9f05fe0a1d67
|
4
|
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Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors, file e384c431-d0c1-d4b2-e053-9f05fe0a1d67
|
4
|
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Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications, file 1d271de8-4983-47d8-8750-10e386341e80
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3
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Nuclear data uncertainty quantification in the ARC fusion reactor, file 4f3d3d8b-b173-44a4-89f4-0a477330fcf3
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3
|
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Code-to-code SIMMER/FRENETIC comparison for the multiphysics simulation of the ALFRED core, file 5c8fe165-843a-417b-b968-2bbb7d58fbc5
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3
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Uncertainty quantification in FRENETIC calculations of ALFRED lead-cooled fast reactor, file 9f55998d-9a41-4672-9ef2-de9184b71c69
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3
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Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis, file d638031b-be7a-4d69-bf25-09a6b14945b4
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3
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Evaluation of the neutron activation of JET in-vessel components following DT irradiation, file e384c42e-30f1-d4b2-e053-9f05fe0a1d67
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3
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A re-visitation of space asymptotic theory in neutron transport, file e384c433-2de1-d4b2-e053-9f05fe0a1d67
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3
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Parametric study of the radiative load distribution on the EU-DEMO first wall due to SPI-mitigated disruptions, file e384c434-4fd2-d4b2-e053-9f05fe0a1d67
|
3
|
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Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem, file ff5be89a-ba63-4f00-a1cd-0faaaea9d0e0
|
3
|
|
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors, file 0ef2798c-9fe3-4985-960f-3b893a922aba
|
2
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“On the Foundation of Transport-Driven Diffusion for Neutron Transport Problems”, file 795aa080-f5cf-4958-b51c-13484e28db6e
|
2
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A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design, file 862462e3-0ef5-4697-a6a8-f027305949fc
|
2
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Spectrum features of the eigenvalue formulations in neutron transport, file da130096-0e89-4d5b-8816-d2b18a9b59bf
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2
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A generalised eigenvalue formulation for core-design applications, file dee30e1b-53fd-4fae-a81d-91dfcae02e20
|
2
|
|
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS, file e384c42e-1088-d4b2-e053-9f05fe0a1d67
|
2
|
|
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors, file e384c42e-19f1-d4b2-e053-9f05fe0a1d67
|
2
|
|
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum, file e384c42f-87cd-d4b2-e053-9f05fe0a1d67
|
2
|
|
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics, file e384c430-47a1-d4b2-e053-9f05fe0a1d67
|
2
|
|
NUCLEAR DATA UNCERTAINTY QUANTIFICATION IN MOLTEN SALT REACTORS WITH XGPT, file e384c432-4592-d4b2-e053-9f05fe0a1d67
|
2
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|
A MOC-based neutron kinetics model for noise analysis, file e384c433-26de-d4b2-e053-9f05fe0a1d67
|
2
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A MOC-based neutron kinetics model for noise analysis, file e384c433-5160-d4b2-e053-9f05fe0a1d67
|
2
|
|
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors, file e384c434-331a-d4b2-e053-9f05fe0a1d67
|
2
|
|
Parametric study of the radiative load distribution on the EU-DEMO first wall due to SPI-mitigated disruptions, file e384c434-4fd1-d4b2-e053-9f05fe0a1d67
|
2
|
|
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design, file 0a6c66b7-5040-45ad-841a-3c4a4333a94a
|
1
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A Revisitation of the ENEA TAPIRO Fast Source Reactor Neutronic Capabilities, file 12e81766-cd4e-4028-a741-d3393a20360e
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1
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A generalised eigenvalue formulation for core-design applications, file 2aea360c-2176-42e0-8b5f-cdf1c74da465
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1
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Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses, file 309a8330-c9a6-46d1-9f8a-b80e5aaf46fc
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1
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Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory, file 379a27cb-23ee-47a6-99cd-fb73d94918ab
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1
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Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool, file 3bb86094-b62b-42e7-834b-3d0a6416e81b
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1
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Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design, file 47447643-6917-4560-b52c-1aa86059f986
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1
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Nuclear data uncertainty quantification on PWR spent nuclear fuel as a function of burnup, file 5386264a-5a5e-4c29-b7b9-084eda14db36
|
1
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Studsvik R2 Materials Test Reactor Ad Hoc Depletion Strategy for the Derivation of the Fuel Isotopic Composition of the MPCMIV Benchmark, file 77f64528-b81d-4da1-a056-0805d969e41b
|
1
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Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design, file afe51021-6251-4285-ac48-bef992262907
|
1
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null, file b9b66cef-238e-48e9-9304-a3a73ceb5fa3
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1
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Application of the Polynomial Chaos Expansion to the Uncertainty Propagation in Fault Transients in Nuclear Fusion Reactors: DTT TF Fast Current Discharge, file bcf6fe95-201d-4213-8f31-33b6aadfdac7
|
1
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An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method, file e384c42e-9edd-d4b2-e053-9f05fe0a1d67
|
1
|
|
The Spectral Element Method for Static Neutron Transport
in A_N Approximation. Part I, file e384c42e-a330-d4b2-e053-9f05fe0a1d67
|
1
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Alternative definitions of kinetic parameters for accelerator driven systems, file e384c42e-a331-d4b2-e053-9f05fe0a1d67
|
1
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|
Neutron multiplication and fissile material distribution in a nuclear reactor, file e384c430-c6a9-d4b2-e053-9f05fe0a1d67
|
1
|
|
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project, file e384c431-6d59-d4b2-e053-9f05fe0a1d67
|
1
|
|
Neutron kinetics equations in Apollo3® code for application to noise problems, file e384c432-2d30-d4b2-e053-9f05fe0a1d67
|
1
|
|
Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation, file e384c432-be5b-d4b2-e053-9f05fe0a1d67
|
1
|
|
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method, file e384c433-199e-d4b2-e053-9f05fe0a1d67
|
1
|
|
Measurement of kinetic parameters by oscillated experiments, file e384c433-27aa-d4b2-e053-9f05fe0a1d67
|
1
|
|
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation, file e384c434-5ec8-d4b2-e053-9f05fe0a1d67
|
1
|
|
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code, file e384c434-709a-d4b2-e053-9f05fe0a1d67
|
1
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| Totale |
739 |
Archivio Istituzionale della Ricerca