25 results on '"Amin, Esmat A."'
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2. Utilizing even Plutonium Isotopes as burnable absorbers for controlling the reactivity and power distribution in Pressurized Water Reactors
3. Calculation of dose rates in loss of coolant accident due to double ended rupture of the experimental tangential irradiation beam tube of MTR reactor
4. Study on criticality and reactivity coefficients of VVER-1200 reactor
5. Study of neutronic characteristics for the VVER reactor assembly with five various burnable poisons using MCNPX code
6. Computational study on distribution feasibility of radioactive waste transmutation in accelerator driven system
7. Transmutation performance of uniform and nonuniform distributions of plutonium and minor actinides in TRIGA Mark II ADS reactor
8. Effect of MOX fuel and the ENDF/B-VIII on the AP1000 neutronic parameters calculations by using MCNP6
9. Rod ejection accident analysis for AP1000 with MOX/UOX mixed core loading
10. Effects of Pu and MA uniform and nonuniform distributions on subcritical multiplication of TRIGA Mark II ADS reactor
11. MCNPX calculation of the reactivity worth of actinides OSMOSE samples
12. Neutron yield as a measure of achievement nuclear fusion using a mixture of deuterium and tritium isotopes
13. Calculation of the NEA C5G7 MOX benchmark with MCNP5
14. Burnup and neutronic analysis for UOX and MOX fuel assemblies in VVER reactor
15. Calculation of dose rates in loss of coolant accident due to double ended rupture of the experimental tangential irradiation beam tube of MTR reactor.
16. Calculation of dose rates in loss of coolant accident due to double ended rupture of the experimental tangential irradiation beam tube of MTR reactor
17. Comparison between the calculated and measured dose distributions for four beams of 6 MeV linac in a human-equivalent phantom
18. Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library
19. The Effect of burnable absorbers on neutronic parameters of VVER-1200 reactor
20. Evaluation of subcritical multiplication parameters in MYRRHA-FASTEF accelerator driven system reactor
21. Using Thorium Based Fuel in AP1000: Steady State Analysis
22. Investigation of subcritical multiplication parameters in TRIGA Mark II accelerator driven system
23. Study of the basic safety characteristic parameters of the MINERVE reactor core configurations
24. Neutronic calculation and power maps investigation of PWR critical lattice experiments using WIMSD-5B and CITVAP v3.1 codes
25. Review of shielding computation methodology with emphasis on the experience in the national center of nuclear safety and radiation control
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