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Teknik nuklir adalah penerapan praktis bidang ilmu inti atom yang disarikan dari prinsip-prinsip fisika nuklir dan interaksi antara radiasi dan material. Bidang keteknikan ini mencakup perancangan, pengembangan, percobaan, operasi dan perawatan sistem dan komponen fisi nuklir, khususnya reaktor nuklir, PLTN dan/atau senjata nuklir. Bidang ini juga dapat mencakup studi tentang fisi nuklir, aplikasi radiasi pada kedokteran nuklir, keselamatan nuklir, perpindahan panas, teknologi pengelolaan bahan bakar nuklir, proliferasi nuklir, dan efek limbah radioaktif atau radioaktivitas lingkungan.

Kumpulan Jjudul Skripsi Jurusan Ilmu dan Rekayasa Nuklir

  1. Nuclear renewable oil shale hybrid energy systems : configuration, performance, and development pathways
  2. LWR fuel reactivity depletion verification using 2D full core MOC and flux map data ?
  3. Experimental study of transient pool boiling heat transfer under exponential power excursion on plate-type heater ?
  4. Memory efficient indexing algorithm for physical properties in OpenMC ?
  5. The effect of environment, chemistry, and microstructure on the corrosion fatigue behavior of austenitic stainless steels in high temperature water
  6. Optimization of deep boreholes for disposal of high-level nuclear waste ?
  7. Investigating the educational effectiveness of a science museum exhibit on small modular fusion reactors 
  8. Investigation of sub-meter shields for a low aspect ratio D-T Tokamak fusion reactor
  9. COMSOL finite-element analysis : residual stress measurement of representative 304L/308L weld in spent fuel storage containers 
  10. Nuclear renewable oil shale hybrid energy systems : configuration, performance, and development pathways
  11. Investigating the educational effectiveness of a science museum exhibit on small modular fusion reactors 
  12. Investigation of sub-meter shields for a low aspect ratio D-T Tokamak fusion reactor ?
  13. COMSOL finite-element analysis : residual stress measurement of representative 304L/308L weld in spent fuel storage containers 
  14. Examination of the United States domestic fusion program ?
  15. Loss-of-flow analysis of an unfinned, graded fuel meat, LEU monolithic U-10Mo fuel design in support of the MITR-II fuel conversion 
  16. Load following operation of a pressurized water nuclear power plant/
  17. Pipe wall damage morphology measurement methodology development for flow assisted corrosion evaluation ?
  18. CANDU pressure/calandria tube emergency water injection system ?
  19. The finite element method applied to neutron diffusion problems. ?
  20. Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients ?