| Nome |
# |
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LFR safety approach and main ELFR safety analysis results, file e0d6c926-43e0-fcf8-e053-d805fe0aa794
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164
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Rigorous Dynamic Simulation of Cryogenic Distillation of Hydrogen Isotopologues in the Fuel Cycle of a Thermonuclear Reactor Based on UV Flash, file e0d6c92d-b5a8-fcf8-e053-d805fe0aa794
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140
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Experimental Evaluation of thermal conductivity of ceramic pebble beds, file e0d6c926-4453-fcf8-e053-d805fe0aa794
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118
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Numerical-experimental analyses by Hot-Wire method of an alumina cylinder for future studies on thermal conductivity of the fusion breeder materials, file e0d6c926-44b4-fcf8-e053-d805fe0aa794
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117
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Manufacturing challenges and required R&D on fusion pebbles bed material, file e0d6c929-f2bf-fcf8-e053-d805fe0aa794
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49
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RELAP5/SIMMER-III code coupling development for PbLi-water interaction, file e0d6c92e-46f7-fcf8-e053-d805fe0aa794
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43
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Preliminary analysis of an aged RPV subjected to station blackout, file e0d6c932-1a2a-fcf8-e053-d805fe0aa794
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37
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Experimental investigation of functional performance of a vacuum vessel pressure suppression system of ITER, file e0d6c929-d32a-fcf8-e053-d805fe0aa794
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24
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An improved substructuring approach for dynamic modelling – The example of the ITER vacuum vessel, file e0d6c92f-159e-fcf8-e053-d805fe0aa794
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14
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Lithium orthosilicate as nuclear fusion breeder material: Optimization of the drip casting production technology, file 4fe72d5e-f9d0-4aff-b6f7-d4a4a34e18a8
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12
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Mitigation of a Loss of Coolant Accident in ITER Vacuum Vessel by Means of Steam Pressure Suppression, file e0d6c92e-4982-fcf8-e053-d805fe0aa794
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11
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Manufacturing technology of ceramic pebbles for breeding blanket, file e0d6c92b-39c7-fcf8-e053-d805fe0aa794
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10
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PRELIMINARY EVALUATION OF CORE COMPACTION PHENOMENON: METHODOLOGICAL APPROACH, file e0d6c926-42af-fcf8-e053-d805fe0aa794
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9
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Manufacturing Technology And Properties Of Ceramic Pebbles For Breeding Blanket, file e0d6c92a-4eae-fcf8-e053-d805fe0aa794
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9
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Structural performance of an IP2 package in free drop test conditions: numerical and experimental evaluations, file e0d6c927-0481-fcf8-e053-d805fe0aa794
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8
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Handling and conditioning techniques of activated chips for the decommissioning of the E. Fermi nuclear power plant, file e0d6c928-8241-fcf8-e053-d805fe0aa794
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8
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CHARACTERIZATION OF FUTURIX-FTA IRRADIATED NUCLEAR FUEL SAMPLES, file e0d6c929-3973-fcf8-e053-d805fe0aa794
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8
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Benefits of Seismic Isolation for Nuclear Structures Subjected to Severe Earthquake, file e0d6c92b-7e01-fcf8-e053-d805fe0aa794
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8
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Preliminary study of the effects of ageing on the long-term performance of NPP pipe, file e0d6c932-0ef4-fcf8-e053-d805fe0aa794
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8
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Safety analysis results of the DBC transients performed for the ALFRED reactor, file e0d6c926-875e-fcf8-e053-d805fe0aa794
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7
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Preliminary Evaluation of the Fluid-Structure Effects in a LFR, file e0d6c926-815b-fcf8-e053-d805fe0aa794
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6
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Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor, file e0d6c926-82ad-fcf8-e053-d805fe0aa794
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6
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Demonstration of structural performance of IP-2 package by simulation and full-scale horizontal free drop test, file e0d6c926-a536-fcf8-e053-d805fe0aa794
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6
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Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant, file e0d6c92a-975f-fcf8-e053-d805fe0aa794
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5
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Analysis of feasibility of a new core catcher for the in-vessel core melt retention strategy, file e0d6c92f-381c-fcf8-e053-d805fe0aa794
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5
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Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor, file e0d6c932-4794-fcf8-e053-d805fe0aa794
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5
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Characterization of the thermal conductivity for ceramic pebble beds, file e0d6c928-820a-fcf8-e053-d805fe0aa794
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4
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METHODOLOGY TO INVESTIGATE VIBRATION PHENOMENA CAUSED BY THE STEAM CONDENSATION AT SUB-ATMOSPHERIC CONDITION, file e0d6c929-3689-fcf8-e053-d805fe0aa794
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4
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Experimental investigation of steam condensation in water tank at sub-atmospheric pressure, file e0d6c92b-39c5-fcf8-e053-d805fe0aa794
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4
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null, file e0d6c926-af5e-fcf8-e053-d805fe0aa794
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3
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Investigation of liquid metal embrittlement of AISI 316L steels, file e0d6c928-88ee-fcf8-e053-d805fe0aa794
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3
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Thermal tests of a scaled down mock-up of CP5.2 packaging system: Post-test analysis, file e0d6c92b-39c1-fcf8-e053-d805fe0aa794
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3
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|
EM zooming procedure in ANSYS Maxwell 3D, file e0d6c92b-39c3-fcf8-e053-d805fe0aa794
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3
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Feasibility study of a new fabrication method for the Li4Sio4 pebbles, file e0d6c92c-61d9-fcf8-e053-d805fe0aa794
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3
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Preliminary investigation of Li4SiO4 pebbles structural performance, file e0d6c931-db76-fcf8-e053-d805fe0aa794
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3
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Aircraft impact effects on an aged NPP, file e0d6c931-eca5-fcf8-e053-d805fe0aa794
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3
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Preliminary Feasibility Study Of Coupling Between
SMR And Desalination Plant, file 1495b64c-fc51-49b7-a821-48c248ad4e0b
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2
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Thermo-mechanical test rig for experimental evaluation of thermal conductivity of ceramic pebble beds, file e0d6c926-4095-fcf8-e053-d805fe0aa794
|
2
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|
Preliminary evaluation of aircraft impact on a near term nuclear power plant, file e0d6c926-4467-fcf8-e053-d805fe0aa794
|
2
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Inclined DROP test of A CC-440 packaging system, file e0d6c928-82c1-fcf8-e053-d805fe0aa794
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2
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Post-test of the sgtr experimental tests carried out in the LIFUS facility, file e0d6c928-8443-fcf8-e053-d805fe0aa794
|
2
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|
Characterization of the thermal conductivity for ceramic pebble beds, file e0d6c928-874d-fcf8-e053-d805fe0aa794
|
2
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Analysis of the effects caused by the core compaction into LFR reactor, file e0d6c928-887b-fcf8-e053-d805fe0aa794
|
2
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|
Experimental thermal characterization of concrete to be used in CP5.2 packaging system, file e0d6c928-e64f-fcf8-e053-d805fe0aa794
|
2
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|
Experimental analysis of steam condensation patterns within a pressure suppression system operating at sub-atmospheric pressure conditions, file e0d6c92d-8a43-fcf8-e053-d805fe0aa794
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2
|
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Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance, file 9ff970cf-5898-4a52-9940-df9e3723606e
|
1
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|
Safety analysis results of the DBC transients performed for the ALFRED reactor, file a34747c3-1603-43bf-9459-f9ebb5081a91
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1
|
|
Application of PHADEC method for the decontamination of radioactive steam piping components of Caorso plant, file e0d6c926-428a-fcf8-e053-d805fe0aa794
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1
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Preliminary evaluation of the seismic response of the ELSY LFR, file e0d6c926-43e6-fcf8-e053-d805fe0aa794
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1
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Influence of aircraft impact on seismic isolated SMR reactor, file e0d6c926-445c-fcf8-e053-d805fe0aa794
|
1
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Preliminary evaluation of seismic isolation effects in a Generation IV reactor, file e0d6c926-4462-fcf8-e053-d805fe0aa794
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1
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null, file e0d6c926-8157-fcf8-e053-d805fe0aa794
|
1
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|
Safety performance of a near surface repository subject to a fuel burning, file e0d6c926-815d-fcf8-e053-d805fe0aa794
|
1
|
|
Investigation on thermal treatments of high-resistance austenitic stainless steels employed as structural materials in generation IV reactors, file e0d6c928-7bb7-fcf8-e053-d805fe0aa794
|
1
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|
Fluid dynamics analysis of loss of vacuum accident of ITER cryostat, file e0d6c928-824a-fcf8-e053-d805fe0aa794
|
1
|
|
Thermo-mechanical characterization of ceramic pebbles for breeding blanket, file e0d6c928-827d-fcf8-e053-d805fe0aa794
|
1
|
|
Experimental thermal characterization of concrete to be used in CP5.2 packaging system, file e0d6c928-85e2-fcf8-e053-d805fe0aa794
|
1
|
|
Investigation of the behaviour of a LILW superficial repository under aircraft impact, file e0d6c928-870a-fcf8-e053-d805fe0aa794
|
1
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|
Dismantling of the graphite pile of Latina NPP: Characterization and handling/removal equipment for single brick or multi-bricks, file e0d6c928-8740-fcf8-e053-d805fe0aa794
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1
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|
null, file e0d6c928-8a5f-fcf8-e053-d805fe0aa794
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1
|
|
Integrity of pressure vessel lower head in case of corium relocation: identification of loads and failure modes, file e0d6c929-f1ea-fcf8-e053-d805fe0aa794
|
1
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Innovative engineering safeguards to cope with corium relocation: Identification of loads and failure modes, file e0d6c92e-1b4f-fcf8-e053-d805fe0aa794
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1
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Computational fluid dynamics thermal analysis of ITER pressure suppression tanks, file e0d6c92f-1991-fcf8-e053-d805fe0aa794
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1
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Numerical analysis of sub-atmospheric steam condensation in suppression tank with SIMMER IV code, file e0d6c92f-3aa6-fcf8-e053-d805fe0aa794
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1
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Inverse Heat Conduction Problem in Estimating NPP Pipeline Performance, file e0d6c92f-6967-fcf8-e053-d805fe0aa794
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1
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Preliminary Analysis of Long-Term Performance of a Piping: Aging and Creep Effects, file e0d6c931-fb98-fcf8-e053-d805fe0aa794
|
1
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|
null, file e93c4608-d1c7-4502-97c3-f6de0b8a5d5c
|
1
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| Totale |
910 |