39 results on '"Schumacher, G."'
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2. Effect of oxygen concentration and temperature on compatibility of ODS steel with liquid, Stagnant Pb 45Bi 55
3. Behavior of steels in flowing liquid PbBi eutectic alloy at 420–600 °C after 4000–7200 h
4. Control of oxygen concentration in liquid lead and lead–bismuth
5. Results of steel corrosion tests in flowing liquid Pb/Bi at 420–600 °C after 2000 h
6. Investigation on oxygen controlled liquid lead corrosion of surface treated steels
7. Changes in hardness and elasticity of a Ti6Al4V alloy under helium irradiation
8. The effect of ion irradiation on microstructural evolution and mechanical properties of NiP and NiCrP brazed joints of austenitic steel
9. Heat transfer and technological investigations on mixed beds of beryllium and Li4SiO4 pebbles
10. Mechanical properties of 10 MeV Xe3+ irradiated Cu and CuA125
11. Non-equilibrium structures induced by ion irradiation in Ni4Mo
12. Preface
13. Stability of phases in joints brazed with Ni-P (BNi6) and Ni-Cr-P (BNi7) alloys under 300 keV Ni+ ion irradiation
14. Stability of phases in joints brazed with Ni$z.sbnd;P (BNi6) and Ni$z.sbnd;Cr$z.sbnd;P (BNi7) alloys under 300 keV Ni+ ion irradiation
15. Information on the evolution of severe LWR fuel element damage obtained in the CORA program
16. Preface
17. R & D work for the lithium orthosilicate pebbles for the Karlsruhe ceramic breeder blanket
18. Research and development work for the lithium orthosilicate pebbles for the Karlsruhe ceramic breeder blanket
19. Results of steel corrosion tests in flowing liquid Pb/Bi at 420-600 degreeC after 2000 h
20. Some thermochemical studies of cesium uranate, molybdate and chromate
21. Oxygen redistribution in fast reactor oxide fuel
22. Study of adsorption and desorption of water on Li4SiO4
23. The LISA-2 experiment: In-situ tritium release from lithium orthosilicate (Li4SiO4)
24. Out-of-pile tritium extraction from lithium silicate
25. Properties of lithium orthosilicate spheres
26. Preface
27. Auswirkungen der ausgangsstöchiometrie auf das betriebsverhalten von oxidischen brennstäben schneller reaktoren
28. Solubility and migration of fission product barium in oxide fuel
29. Structure and composition changes in nuclear fuel in simulated loss-of-flow transients
30. Redistribution of uranium and plutonium during evaporation processes in mixed oxide fuel
31. Considerations on PyC and SiC coated oxide particles for gas cooled fast reactor application
32. Considerations on the oxygen distribution in hypostoichiometric mixed oxide fuel pins
33. Plutonium redistribution in fast reactor mixed oxide fuel pins
34. Redistribution of plutonium and uranium in mixed (U, Pu) oxide fuel materials in a thermal gradient
35. Theoretische betrachtungen über die eignung von vanadiumlegierungen als hüllwerkstoff für oxidische (U, Pu)-kernbrennstoffe
36. Thermodiffusion im system UO2CeO2
37. Mechanical properties of 10 MeV Xe 3+ irradiated Cu and CuA125
38. Heat transfer and technological investigations on mixed beds of beryllium and Li 4SiO 4 pebbles
39. Stability of phases in joints brazed with Ni-P (BNi6) and Ni-Cr-P (BNi7) alloys under 300 keV Ni + ion irradiation
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