1,639 results on '"HEAT resistant materials"'
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2. American Vacuum Society national symposium, 26th, New York, N. Y. , October 1-5, 1979, proceedings
3. Design of D9: a radiation damage-resistant alloy
4. Materials research for clean utilization of coal. Quarterly progress report, October--December 1977
5. State-variable analysis of inelastic deformation of thin-walled tubes. II. Data analysis and simulations. [LMFBR]
6. Tenth ADIP quarterly progress report
7. State-variable analysis of inelastic deformation of thin-walled tubes. I. Modelling. [LMFBR]
8. Corrosion behaviour of engineering materials at elevated temperatures in an oxidising environment containing sulphur derivatives: influence of the composition of aggressive media and of the alloys under test (tenue a la corrosion a temperature elevee de materiaux par les milieux oxydants contenant des derives soufres: influence de la composition des phases agressives et des alliages exprimentes). Final report
9. Task group B: swelling behavior of advanced alloys. Second quarterly report. [LMFBR]
10. Low temperature hydrothermal processing of organic contaminants in Hanford tank waste
11. Effects of internal helium on mechanical properties of NITRONIC[trademark] 40 stainless steel
12. Effects of temperature and radiation on the nuclear waste glass product consistency leach test
13. Fuel/cladding compatibility in high-burnup U-19Pu-10Zr/HT9-clad fuel at elevated temperatures
14. Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests
15. Mechanical properties of martensitic alloy AISI 422
16. Stress corrosion cracking susceptibility of irradiated Type 304 stainless steels
17. Corrosion resistance of iron aluminides
18. Fill tube bore inspection with machine vision
19. Orientation dependency of mechanical properties of 1950's vintage Type 304 stainless steel weldment components before and after low temperature neutron irradiation
20. Selection of non-adsorbing alkali components
21. Excimer laser surface modification: Process and properties
22. Investigation of azimuthal stresses due to welding and cooldown
23. Experience with advanced driver fuels in EBR-II
24. Evaluation of liquid metal embrittlement of SS304 by Cd and Cd-Al solutions
25. Performance of HT9 clad metallic fuel at high temperature
26. Resistance upset welding for vessel fabrication
27. Irradiation-induced sensitization and stress corrosion cracking of Type 304 stainless steel core-internal components
28. Ultrasonic characterization of laser ablation
29. Excimer laser surface processing for tribological applications in metals and ceramics
30. Mechanical properties of 1950's vintage 304 stainless steel weldment components after low temperature neutron irradiation
31. Elevated temperature tensile properties of borated 304 stainless steel: Effect of boride dispersion on strength and ductility
32. Type B plutonium transport package development that uses metallic filaments and composite materials
33. Irradiation experience with HT9-clad metallic fuel
34. Irradiation-induced sensitization of austenitic stainless steel in-core components
35. Irradiation-assisted stress corrosion cracking of fusion reactor material
36. Conical surface textures formed by ion bombarding 2% Be Cu alloy
37. A failure probability estimate of Type 304 stainless steel piping
38. Effect of internal gas pressure on the shock consolidation of 304 stainless steel powders
39. Mechanical properties of 1950's vintage Type 304 stainless steel weldment components
40. Computational modeling of GTA (gas tungsten arc) welding with emphasis on surface tension effects
41. Interactions at glass-ceramic to metal interfaces
42. Development of coatings with improved corrosion resistance in sulfur-containing environments
43. Evaluation of radiation-induced sensitization using electrochemical potentiokinetic reactivation technique for austenitic stainless steels
44. The effect of aging at 343 degrees C on type 308 stainless steel weldments
45. SR's reactor tank inspection program: UT development, application, and results
46. Weld overlay coatings for erosion control
47. Reactor Materials Program -- weldment component toughness of SRS PWS piping materials. [Process Water System]
48. Corrosion fatigue of iron-chromium-nickel alloys: Fracture mechanics, microstructure and chemistry
49. Requirements for characterization of DWPF canister welds and labels, and estimates of service life
50. Friction microprobe investigation of particle layer effects on sliding friction
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