26 results on '"Mansani, L."'
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2. Identification and categorisation of safety issues for ESNII reactor concepts. Part I: Common phenomena related to materials
3. Study of a Low-power, Fast-neutron-based ADS
4. An intrinsically safe facility for forefront research and training on nuclear technologies — General description of the system
5. Important viewpoints proposed for a safety approach of HTGR reactors in Europe: Final results of the EC-funded HTR-L project
6. Safety Analysis of the EU PDS-XADS Designs
7. Safety analysis results of the DBC transients performed for the ALFRED reactor
8. LFR safety approach and main ELFR safety analysis results
9. Status and Trend of Core Design Activities for Heavy Cooled Accelerator Driven System
10. Study of a low-power, fast-neutron-based ADS
11. General Synthesis Report of the Different ADS Design Status. Establishment of a Catalogue of the R&D needs
12. Achievements and lessons learned within the Domain 1 'DESIGN' of the IP_EUROTRANS Integrated Project
13. Secondary Loop Design and Off-Design Operation of an Accelerator-Driven Reactor for the Exploitation of Nuclear Wastes
14. Centrali Nucleari al Piombo: Analisi di Cicli Termodinamici per il Circuito Secondario
15. Development and assessment of structural materials and heavy liquid metal technologies for transmutation systems (DEMETRA): highlights on major results
16. Design and R&D support of the XT-ADS Spallation Target
17. DM1 DESIGN: Development of a Detailed Design of XT-ADS and of a Conceptual Design of EFIT with Heavy Liquid Metal Cooling
18. Design and Supporting R&D of the XT-ADS Spallation Target
19. Safety Analysis Results of Representative DEC Accidental Transients for the ALFRED Reactor
20. Main achievements of the FP7-LEADER collaborative project of the european commission regarding the design of a lead-cooled fast reactor
21. Passive system for Distributed Heat removal from Containment
22. The European Lead-Cooled EFIT Plant: An Industrial-Scale Accelerator-Driven System for Minor Actinide Transmutation—I
23. Neutronic Assessment and Criticality Analysis of the In-Vessel Fuel Storage Facilities in the CDT Project
24. Proposal for pressure drop prediction for a fuel bundle with grid spacers using Rehme pressure drop correlations
25. A preliminary study of an improved area method, adapted to short time transients in sub-critical systems
26. Conceptual design and optimization for a low-power ADS with a 70 MeV, 0.75 mA proton beam
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