241 results on '"Mansur, L.K."'
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2. Post-irradiation examination of the Spallation Neutron Source target module
3. Perspectives on radiation effects in nickel-base alloys for applications in advanced reactors
4. Cavitation-erosion resistance of 316LN stainless steel in mercury containing metallic solutes
5. Summary of the 7th International Workshop on Spallation Materials Technology (IWSMT-7)
6. Status of the Spallation Neutron Source with focus on target materials
7. Fatigue properties of type 316LN stainless steel in air and mercury
8. Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences
9. The effect of mean stress on the fatigue behavior of 316 LN stainless steel in air and mercury
10. Effects of mercury on fatigue behavior of Type 316 LN stainless steel: application in the spallation neutron source
11. Materials research and development for the spallation neutron source mercury target
12. Microstructural analysis of ion-irradiation-induced hardening in inconel 718
13. Ion beam application for improved polymer surface properties**Research sponsored in part by the U.S. Department of Energy, Assistant Secretary of Conservation and Renewable Energy, Office of Industrial Technologies, Advanced Industrial Concepts (AIC) Materials Program, in part by the Division of Materials Sciences, U.S. Department of Energy under contract No. DE-AC05–84OR21400 with Martin Marietta Energy Systems, Inc. and in part by the Exploratory Studies Program of Oak Ridge National Laboratory.
14. Temperature effects on the mechanical properties of candidate SNS target container materials after proton and neutron irradiation
15. On the origin of deformation microstructures in austenitic stainless steel: part I—microstructures
16. Influence of mercury environment on the fatigue behavior of spallation neutron source (SNS) target container materials
17. Strain hardening and plastic instability properties of austenitic stainless steels after proton and neutron irradiation
18. Summary of the Fourth International Workshop on Spallation Materials Technology (IWSMT-4)
19. Origin of hardening and deformation mechanisms in irradiated 316 LN austenitic stainless steel
20. R&D for the Spallation Neutron Source mercury target
21. Ion-irradiation-induced hardening in Inconel 718
22. Simulation of the implantation of recoils and displacement production in the 316 stainless steel mercury-container vessel at SNS
23. Radiation damage to the 316 stainless steel target container vessel at SNS
24. Characterization of plastic deformation in a disk bend test
25. Effects of helium on radiation-induced defect microstructure in austenitic stainless steel
26. Hardness and defect structures in EC316LN austenitic alloy irradiated under a simulated spallation neutron source environment using triple ion-beams
27. Fe–15Ni–13Cr austenitic stainless steels for fission and fusion reactor applications. III. Phase stability during heavy ion irradiation
28. Fe–15Ni–13Cr austenitic stainless steels for fission and fusion reactor applications. II. Effects of minor elements on precipitate phase stability during thermal aging
29. Fe–15Ni–13Cr austenitic stainless steels for fission and fusion reactor applications. I. Effects of minor alloying elements on precipitate phases in melt products and implication in alloy fabrication
30. Helium and hydrogen induced hardening in 316LN stainless steel
31. LET effect on cross-linking and scission mechanisms of PMMA during irradiation
32. Triple ion beam studies of radiation damage in 9Cr–2WVTa ferritic/martensitic steel for a high power spallation neutron source
33. Irradiation creep at temperatures of 400 {degrees}C and below for application to near-term fusion devices
34. The half-century of nuclear materials
35. Preface
36. Spallation materials R&D: Remarks on progress and future
37. Foreword
38. Irradiation creep by climb-enabled glide of dislocations resulting from preferred absorption of point defects
39. Cascade diffusion theory of sink capture fluctuations during irradiation of a solid
40. Study of the effect of void surface coatings on radiation-induced swelling
41. Hardness Enhancement and Crosslinking Mechanisms in Polystyrene Irradiated with High Energy Ion-Beams
42. Mechanisms of radiation-induced degradation of reactor vessel materials
43. Theory and experimental background on dimensional changes in irradiated alloys
44. An evaluation of low temperature radiation embrittlement mechanisms in ferritic alloys
45. Wear properties of argon implanted poly(ether ether ketone)
46. Homogeneous reaction rate model for hydrogen production from ion-irradiated polymers
47. Summary of Montreux Workshop on “time dependence of radiation damage accumulation and its impact on materials properties”
48. Theory of transitions in dose dependence of radiation effects in structural alloys
49. Structure and dose effects on improved wear properties of ion-implanted polymers
50. Ion beam application for improved polymer surface properties
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