| Nome |
# |
|
Uncertainty quantification method for RELAP5-3D© using RAVEN and application on NACIE experiments, file e3835323-0f9c-15e8-e053-a505fe0a3de9
|
327
|
|
GEN-IV LFR development: Status & perspectives, file e3835323-6342-15e8-e053-a505fe0a3de9
|
278
|
|
Investigation on RELAP5-3D© capability to predict thermal stratification in liquid metal pool-type system and comparison with experimental data, file e3835322-cebe-15e8-e053-a505fe0a3de9
|
267
|
|
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment, file e3835321-af4c-15e8-e053-a505fe0a3de9
|
219
|
|
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion Project, file e3835321-9884-15e8-e053-a505fe0a3de9
|
215
|
|
Post-test simulations for the NACIE-UP benchmark by STH codes, file e3835323-1077-15e8-e053-a505fe0a3de9
|
205
|
|
In-box LOCA accident analysis for the European DEMO water-cooled reactor, file e3835321-7cd2-15e8-e053-a505fe0a3de9
|
202
|
|
MHD mixed convection flow in the WCLL: heat transfer analysis and cooling system, file e3835321-875b-15e8-e053-a505fe0a3de9
|
191
|
|
Pool temperature stratification analysis in CIRCE-ICE facility with RELAP5-3D© model and comparison with experimental tests, file e3835318-7890-15e8-e053-a505fe0a3de9
|
163
|
|
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test, file e3835326-ba58-15e8-e053-a505fe0a3de9
|
163
|
|
Improvements of RELAP5/Mod3.3 heat transfer capabilities for simulation of in-pool passive power removal systems, file e383532c-7b4a-15e8-e053-a505fe0a3de9
|
150
|
|
Thermal-hydraulic assessment of Once-Through Steam Generators for EU-DEMO WCLL Breeding Blanket primary cooling system application, file c9c8d910-5919-4db7-a8f3-8153fd48801b
|
144
|
|
New RELAP5-3D Lead and LBE Thermophysical Properties Implementation for Safety Analysis of Gen IV Reactors, file e3835314-7416-15e8-e053-a505fe0a3de9
|
141
|
|
Preliminary neutron kinetic. Thermal hydraulic coupled analysis of the ALFRED reactor using PHISICS/RELAP5-3D, file e3835328-0328-15e8-e053-a505fe0a3de9
|
140
|
|
Development of a RELAP5/MOD3.3 module for MHD pressure drop analysis in liquid metals loops. Verification and validation, file e383532c-a924-15e8-e053-a505fe0a3de9
|
132
|
|
Pre-test analysis of protected loss of primary pump transients in CIRCE-HERO facility, file e3835318-983b-15e8-e053-a505fe0a3de9
|
126
|
|
Preliminary MHD pressure drop analysis for the prototypical WCLL TBM with RELAP5/MOD3.3, file e383532e-2ba6-15e8-e053-a505fe0a3de9
|
124
|
|
CFD analysis of WCLL BB PbLi manifold, file e383531c-e296-15e8-e053-a505fe0a3de9
|
120
|
|
Numerical analysis of temperature stratification in the CIRCE pool facility, file e3835323-873b-15e8-e053-a505fe0a3de9
|
118
|
|
Analysis of unmitigated large break loss of coolant accidents using MELCOR code, file e383531a-746b-15e8-e053-a505fe0a3de9
|
115
|
|
Experimental analysis of stationary and transient scenarios of ALFRED steam generator bayonet tube in CIRCE-HERO facility, file e3835323-106e-15e8-e053-a505fe0a3de9
|
115
|
|
MYRRHA primary heat exchanger experimental simulations on CIRCE-HERO, file e3835323-15f2-15e8-e053-a505fe0a3de9
|
115
|
|
Thermal-hydraulic transient analysis of the FFTF LOFWOS Test #13, file e383532d-0007-15e8-e053-a505fe0a3de9
|
113
|
|
A Preliminary Exergy Analysis of the EU DEMO Fusion Reactor, file e3835323-0b82-15e8-e053-a505fe0a3de9
|
112
|
|
Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility, file e3835323-4210-15e8-e053-a505fe0a3de9
|
107
|
|
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark, file e3835323-6ef5-15e8-e053-a505fe0a3de9
|
105
|
|
Study of EU DEMO WCLL breeding blanket and primary heat transfer system integration, file e383532a-d6f1-15e8-e053-a505fe0a3de9
|
105
|
|
The DEMO water-cooled lead–lithium breeding blanket: design status at the end of the pre-conceptual design phase, file e383532d-d55c-15e8-e053-a505fe0a3de9
|
102
|
|
Thermal-hydraulic analysis of an innovative decay heat removal system for lead-cooled fast reactors, file e383532a-bcf2-15e8-e053-a505fe0a3de9
|
101
|
|
Design and integration of the EU-DEMO water-cooled lead lithium breeding blanket, file e47c6f7d-9f16-4b25-a22a-3610a97bb577
|
99
|
|
Sizing of the Vacuum Vessel Pressure Suppression System of a Fusion Reactor Based on a Water-Cooled Blanket, for the Purpose of the Preconceptual Design, file e3835315-e083-15e8-e053-a505fe0a3de9
|
97
|
|
Advancements in DEMO WCLL breeding blanket design and integration, file e383532a-765e-15e8-e053-a505fe0a3de9
|
96
|
|
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module, file e3835326-041f-15e8-e053-a505fe0a3de9
|
90
|
|
Numerical study of laminar magneto-convection in a differentially heated square duct, file e3835321-9cad-15e8-e053-a505fe0a3de9
|
86
|
|
Study of the EU-DEMO WCLL breeding blanket primary cooling circuits thermal-hydraulic performances during transients belonging to LOFA category, file e383532c-086a-15e8-e053-a505fe0a3de9
|
85
|
|
Experimental investigation on circe-hero for the eu demo pbli/water heat exchanger development, file e383532c-18ae-15e8-e053-a505fe0a3de9
|
83
|
|
Development of a Steam Generator Mock-Up for EU DEMO Fusion Reactor: Conceptual Design and Code Assessment, file 2db54cd4-8991-4003-b419-32affad3e81e
|
82
|
|
WCLL breeding blanket design and integration for DEMO 2015: status and perspectives, file e383532a-835e-15e8-e053-a505fe0a3de9
|
75
|
|
Recent progress in the WCLL breeding blanket design for the DEMO fusion reactor, file e383532a-b217-15e8-e053-a505fe0a3de9
|
72
|
|
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor, file e3835327-0a39-15e8-e053-a505fe0a3de9
|
71
|
|
Dynamic event tree analysis as a tool for risk assessment in nuclear fusion plants using RAVEN and MELCOR, file e383532e-b69b-15e8-e053-a505fe0a3de9
|
70
|
|
Preliminary evaluation of ALFRED revised concept under station blackout, file e3835326-5e8c-15e8-e053-a505fe0a3de9
|
68
|
|
Experimental characterization of leak detection systems in HLM pool using LIFUS5/Mod3 facility, file e3835329-70c1-15e8-e053-a505fe0a3de9
|
62
|
|
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System, file e383532a-e9a7-15e8-e053-a505fe0a3de9
|
55
|
|
Conceptual Design of the Steam Generators for the EU DEMO WCLL Reactor, file 191e3b7e-0127-43e3-8ad8-66d48d29a75b
|
51
|
|
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code, file e383532a-713e-15e8-e053-a505fe0a3de9
|
49
|
|
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept, file e3835326-3091-15e8-e053-a505fe0a3de9
|
46
|
|
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances, file e3835327-edcd-15e8-e053-a505fe0a3de9
|
45
|
|
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket, file e383532a-cc79-15e8-e053-a505fe0a3de9
|
43
|
|
Analysis of EU-DEMO WCLL Power Conversion System in Two Relevant Balance of Plant Configurations: Direct Coupling with Auxiliary Boiler and Indirect Coupling, file e383532f-1220-15e8-e053-a505fe0a3de9
|
42
|
|
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident, file e383532a-c41b-15e8-e053-a505fe0a3de9
|
35
|
|
Evaluation of the thermal-hydraulic performances of a once-through steam generator in nuclear fusion applications, file e383532e-e38b-15e8-e053-a505fe0a3de9
|
35
|
|
Pre-test analysis of accidental transients for ALFRED SGBT mock-up characterization, file e383532a-d043-15e8-e053-a505fe0a3de9
|
34
|
|
Analysis of Fukushima Daiichi unit 4 spent fuel pool using MELCOR, file e383532f-00e9-15e8-e053-a505fe0a3de9
|
34
|
|
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste, file 84c4154e-6a49-4a52-ba62-16fc754296cc
|
33
|
|
Severe accident sensitivity and uncertainty estimation using MELCOR and RAVEN, file e383532f-00e7-15e8-e053-a505fe0a3de9
|
33
|
|
Transient analysis of OSU-MASLWR with RELAP5, file e383532f-2529-15e8-e053-a505fe0a3de9
|
33
|
|
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes, file 908f620b-7870-4192-b474-387d9288cb5c
|
32
|
|
Maturation of critical technologies for the DEMO balance of plant systems, file e383532e-9b5c-15e8-e053-a505fe0a3de9
|
29
|
|
Transient analysis of a locked rotor/shaft seizure accident involving the EU-DEMO WCLL Breeding Blanket primary cooling circuits, file 87653324-4ace-465f-ac2a-ead2a934cb64
|
23
|
|
Transient analysis of SIRIO using RELAP5/MOD3.3 system code, file d0f897c1-d8bc-404c-8c65-49826f4d2d02
|
22
|
|
Pre-conceptual design of EU DEMO balance of plant systems. Objectives and challenges, file e383532b-1e7b-15e8-e053-a505fe0a3de9
|
21
|
|
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger, file e383532b-602d-15e8-e053-a505fe0a3de9
|
18
|
|
Decontamination and remediation of underground holes and testing of cleaning techniques based on the use of liquid cold decontaminant, file 8af428e7-b437-4e9f-92d9-2aa6401bd1cf
|
15
|
|
CFD Analysis and optimization of the DEMO WCLL central outboard segment bottom-Cap elementary cell, file fe05d13b-1754-4fd9-801b-46825ddc85b3
|
15
|
|
Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis, file e383532c-1814-15e8-e053-a505fe0a3de9
|
14
|
|
Experimental characterization of leak detection systems in HLM pool using LIFUS5/Mod3 facility, file e383532d-f9ff-15e8-e053-a505fe0a3de9
|
14
|
|
Design and optimization of the secondary circuit for the WCLL BB option of the EU-DEMO power plant, file e383532b-ce4d-15e8-e053-a505fe0a3de9
|
13
|
|
Liquid metal turbulent heat transfer in cross-flow bundles for advanced nuclear reactors, file e3835327-141b-15e8-e053-a505fe0a3de9
|
12
|
|
Design and development of a package prototype for intermediate level solid waste (ILW), file e383532c-e273-15e8-e053-a505fe0a3de9
|
12
|
|
Preliminary uncertainty quantification of the core degradation models in predicting the Fukushima Daiichi unit 3 severe accident, file e383532c-b75d-15e8-e053-a505fe0a3de9
|
11
|
|
STEAM. A novel experimental infrastructure for the development of the DEMO BOP water coolant technology, file 74a57b34-c750-405e-aed3-6637c1aed119
|
10
|
|
Development of a PbLi heat exchanger for EU DEMO fusion reactor. Experimental test and system code assessment, file e383532b-5c77-15e8-e053-a505fe0a3de9
|
10
|
|
PbLi/Water Reaction: Experimental Campaign and Modeling Advancements in WPBB EUROfusion Project, file af4dfe60-8222-41cd-8e33-41fdb3bb8583
|
9
|
|
Total loss of flow benchmark in CIRCE-HERO integral test facility, file e383532a-9f85-15e8-e053-a505fe0a3de9
|
9
|
|
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project, file 1f0f7361-5a49-4ec3-955b-548fcf130078
|
7
|
|
Blind simulations of NACIE-UP experimental tests by STH codes, file e3835321-26ab-15e8-e053-a505fe0a3de9
|
7
|
|
STEAM. A novel experimental infrastructure for the development of the DEMO BOP water coolant technology, file f9640b0b-1dbe-4c09-adab-e7833d37c5d1
|
7
|
|
CFD - STH Code Coupling for the Thermal Hydraulic Analysis of NACIE-UP Experimental Facility, file 9ea1dacf-7af0-4251-83e2-c37200ccc2bf
|
5
|
|
Experimental analysis of stationary and transient scenarios of ALFRED steam generator bayonet tube in CIRCE-HERO facility, file e3835323-e458-15e8-e053-a505fe0a3de9
|
5
|
|
Tokamak cooling systems and power conversion system options, file e383532e-6eae-15e8-e053-a505fe0a3de9
|
5
|
|
Dynamic event tree analysis as a tool for risk assessment in nuclear fusion plants using RAVEN and MELCOR, file e383532e-b4f3-15e8-e053-a505fe0a3de9
|
5
|
|
The design of water loop facility for supporting the WCLL breeding blanket technology and safety, file 54b85cac-0a9d-49f0-ab37-2444d894c3ef
|
4
|
|
Status, Design and Thermal-Hydraulic Analyses of the Steam Facility for DEMO WCLL Balance of Plant Systems, file 6d083b3f-726b-4e24-ace7-019a00e1a5b4
|
4
|
|
An alternative solution for heavy liquid metal cooled reactors fuel assemblies, file e3835312-32a5-15e8-e053-a505fe0a3de9
|
4
|
|
Recent progress in the WCLL breeding blanket design for the DEMO fusion reactor, file e383531a-9fc1-15e8-e053-a505fe0a3de9
|
4
|
|
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility, file e3835324-a90b-15e8-e053-a505fe0a3de9
|
4
|
|
Tokamak cooling systems and power conversion system options, file e383532e-bba2-15e8-e053-a505fe0a3de9
|
4
|
|
Experimental investigation on pure steam and steam-air mixture condensation inside Tubes, file 1a3763cb-f0fe-486f-9600-9961d6a31406
|
3
|
|
Iaea's coordinated research projects on thermal hydraulics of fast reactors, file 27514f57-d25d-41f7-8dcf-561346c0cc21
|
3
|
|
OECD/NEA/CSNI/WGAMA PERSEO benchmark. Main outcomes and conclusions, file 47787d5c-8332-45de-aba8-c86717f9e4fa
|
3
|
|
ATHENA main heat exchanger conceptual design and thermal-hydraulic assessment with relap5 code, file 6dd24bab-574f-4383-8e12-ef308b4f76ed
|
3
|
|
The STEAM Facility: Design and Analysis, file da82f57f-6d96-4de1-a645-2d5bc1e8bab8
|
3
|
|
ALFRED-SGBT. Preliminary characterization by the HERO test section, file e3835314-ab15-15e8-e053-a505fe0a3de9
|
3
|
|
Enhanced shuffling and fuel management capability in PHISICS code, file e3835316-2c90-15e8-e053-a505fe0a3de9
|
3
|
|
Advancements in DEMO WCLL breeding blanket design and integration, file e3835317-7831-15e8-e053-a505fe0a3de9
|
3
|
|
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket, file e3835319-ec21-15e8-e053-a505fe0a3de9
|
3
|
|
GEN-IV LFR development: Status & perspectives, file e383531c-507e-15e8-e053-a505fe0a3de9
|
3
|
|
Sirio: An experimental facility for a new heat removal system passively controlled by non-condensable gases, file e3835321-3572-15e8-e053-a505fe0a3de9
|
3
|
|
In-box LOCA accident analysis for the European DEMO water-cooled reactor, file e3835323-40b4-15e8-e053-a505fe0a3de9
|
3
|
| Totale |
6.609 |