171 results on '"Yapıcı, Hüseyin"'
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2. Transient thermal stress distribution in a circular pipe heated externally with a periodically moving heat source
3. Data mining and preprocessing application on component reports of an airline company in Turkey
4. Performance of transition model for predicting low [formula omitted] aerofoil flows without/with single and simultaneous blowing and suction
5. Hydrogen production via water splitting process in a molten-salt fusion breeder
6. TACO-miner: An ant colony based algorithm for rule extraction from trained neural networks
7. Classification rule discovery for the aviation incidents resulted in fatality
8. Utilization of heavy metal molten salts in the ARIES-RS fusion reactor
9. Hydrogen production via water splitting process in a molten-salt fusion breeder
10. Performance of transition model for predicting low Re aerofoil flows without/with single and simultaneous blowing and suction
11. On the neutronic performance of HYLIFE-II reactor fuelled with carbide fuels
12. Utilization of heavy metal molten salts in the ARIES-RS fusion reactor
13. Hydrogen production via water splitting process in a molten-salt fusion breeder
14. Performance of transition model for predicting low Re aerofoil flows without/with single and simultaneous blowing and suction
15. On the neutronic performance of HYLIFE-II reactor fuelled with carbide fuels
16. A comprehensive study on neutronics of a lead–bismuth eutectic cooled accelerator-driven sub-critical system for long-lived fission product transmutation
17. Modification of PROMETHEUS Reactor as a Fusion Breeder and Fission Product Transmuter
18. Utilization of Heavy Metal Molten Salts in the ARIES-RS Fusion Reactor
19. Time-dependent Neutronic Analysis for High Level Waste Transmutation in a Fusion-driven Transmuter
20. Neutronic Analysis for Transmutation of Minor Actinides and Long-Lived Fission Products in a Fusion-Driven Transmuter (FDT)
21. Effect of oxygen fraction on local entropy generation in a hydrogen–air burner
22. Study on transient local entropy generation in pulsating fully developed laminar flow through an externally heated pipe
23. On the Neutronic Performance of Hylife-II Reactor Fuelled with Carbide Fuels
24. Neutronic limits in infinite target mediums driven by high energetic protons
25. Reduction of thermally induced stress in a solid disk heated with radially periodic expanding and contracting ring heat flux
26. Transmutation–incineration potential of transuraniums discharged from PWR-UO 2 spent fuel in modified PROMETHEUS fusion reactor
27. Study on spent fuel rejuvenation in PROMETHEUS fusion reactor
28. Numerical solutions of transient temperature and thermally induced stress distributions in a solid disk heated with radially periodic expanding and contracting ring heat flux
29. Numerical calculation of local entropy generation in a methane–air burner
30. Neutronic analysis of denaturing plutonium in a thorium fusion breeder and power flattening
31. Numerical study on conjugate heat transfer in laminar fully developed flow with temperature dependent thermal properties through an externally heated SiC/SiC composite pipe and thermally induced stress
32. Numerical solutions of transient conjugate heat transfer and thermally induced stress distribution in a heated and rotating hollow disk
33. Integral data for most important materials, namely lithium, beryllium, lead and uranium in infinite medium per fusion neutron
34. Numerical solutions of conjugate heat transfer and thermal stresses in a circular pipe externally heated with non-uniform heat flux
35. CFD modeling of conjugate heat transfer and homogeneously mixing two different fluids in a stirred and heated hemispherical vessel
36. Study of fissile fuel breeding concept for the force-free helical reactor
37. Power flattening of an inertial fusion energy breeder with mixed ThO 2–UO 2 fuel
38. Determination of the optimal plutonium fraction in transuranium discharged from pressured water reactor (PWR) spent fuel for a flat fission power generation in the force-free helical reactor (FFHR) along the transmutation period
39. Study on transmutation of minor actinides discharged from high burn-up PWR-MOX spent fuel in the force-free helical reactor
40. Power flattening in Prometheus breeder reactor using nuclear fuel and waste actinide
41. Burning and/or transmutation of transuraniums discharged from PWR-UO 2 spent fuel and power flattening along the operation period in the force free helical reactor
42. Neutronic performance of coupled hybrid blanket fueled with ThO 2 and UO 2
43. Investigation of the performance parameters and temperature distribution in fuel rod dependent on operation periods and first wall loads in fusion–fission reactor system fueled with ThO 2
44. Temperature distribution in mixed ThO 2–UO 2 fuel rods located in blanket of an inertial fusion energy breeder
45. Neutronic analysis of PROMETHEUS reactor fueled with various compounds of thorium and uranium
46. Neutronic analysis of an inertial fusion energy breeder with SiC f/SiC
47. Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D–T) driven hybrid reactor system
48. Neutronic performance of proliferation hardened thorium fusion breeders
49. Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel
50. Analysis of the rejuvenation performance of hybrid blankets by using uranium fuels (UN, UC, UO 2, U 3Si 2) and different coolants for various volume fraction
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