37 results on '"Struwe, D."'
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2. Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis
3. High performance light water reactor
4. Accident analyses and passive measures reducing the consequences of a core-melt in CAPRA/CADRA reactor cores
5. Status and Trend of Core Design Activities for Heavy Cooled Accelerator Driven System
6. General Synthesis Report of the Different ADS Design Status. Establishment of a Catalogue of the R&D needs
7. Achievements and lessons learned within the Domain 1 'DESIGN' of the IP_EUROTRANS Integrated Project
8. Cladding materials performance and the safety of HLM cooled systems
9. Assessment of correlations for heat transfer to the cooland for heavy liquid metal cooled core designs
10. DM1 DESIGN: Development of a Detailed Design of XT-ADS and of a Conceptual Design of EFIT with Heavy Liquid Metal Cooling
11. The TRADE Experiment: Status of the Project and Physics of the Spallation Target
12. Partitioning und Transmutation: Eine neue Perspektive bei der Behandlung nuklearer Abfälle? Patitioning and transmutation: a new perspective for nuclear waste disposal?
13. Untersuchungen von Auslegungs- und schweren Störfällen in Leichtwasserreaktoren. Studies of design basis accidents and severe accidents in light water reactors
14. Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis
15. Modifications of the code SAS4A for simulation of ADS designs
16. Consequence evaluation of in-vessel fuel coolant interactions in the European pressurized water reactor
17. Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation
18. XT-ADS: Neutronics, Shielding, and Radiation Damage Calculations
19. The Potential of the LFR and the ELSY Project
20. Reactivity feedback evaluation of material relocations in the Cabri-1 experiments with fuel worth distributions from SNR-300
21. BACCHUS-3D/SP A computer programme for the three-dimensional description of sodium single-phase flow in bundle geometry
22. Untersuchungen zu Kuehlmitteldurchsatzstoerfaellen im abgebrannten Mark 1A-Kern des Kernkraftwerks Kalkar
23. BLOW-3A, a theoretical model to describe transient two-phase flow conditions in LMFBR coolant channels
24. Das Verhalten des Kerns eines schnellen natriumgekuehlten Brutreaktors von 2000 MWe bei Stoerfaellen sehr geringer Eintrittswahrscheinlichkeit
25. Neutronic design of the XT-ADS core
26. State of development of the computer programme BACCHUS-3D/TP for the description of transient two-phase flow conditions in LMFBR fuel pin bundles
27. Thermohydraulic aspects of the interpretation of the SCARABEE fuel failure experiments
28. Theoretical interpretation of SCARABEE single pin in-pile boiling experiments
29. A simple electronic device for time-lapse recording of neural and other cell movements using a home video cassette recorder
30. Experimental and numerical investigations of sodium boiling experiments in pin bundle geometry
31. Report on the checking of some tests for the simulation of severe hypothetical accidents in fast reactors at the TREAT reactor. Bericht ueber die Nachrechnung einiger Versuche zur Simulation schwerer hypothetischer Unfaelle schneller Reaktoren am TREAT-Reaktor
32. Investigation of space-dependent dynamic behavior of fast breeder reactors with a variation principle using time-discontinuous approximation function. Untersuchung des ortsabhangigen dynamischen verhaltens schneller brutreaktoren unter verwendung eines variationsprinzips mit zeitlich diskontinuierlichen schatzfunktionen
33. Status of analysis of hypothetical core disruptive accident energetics for licensing of SNR-300
34. Space--time-dependent codes and problems of few-group cross-section schemes
35. TWO-DIMENSIONAL MODEL FOR FAST REACTOR KINETICS ANALYSIS WITH SPACE DEPENDENT FEEDBACK.
36. REPORT ON THE CHECKING OF SOME TESTS FOR THE SIMULATION OF SEVERE HYPOTHETICAL ACCIDENTS IN FAST REACTORS AT THE TREAT REACTOR.
37. Calf muscle work and segment energy changes in human treadmill walking.
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