22 results on '"Apostolov, T."'
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2. Two-dimensional diffusion program hexaga II for many-group calculations of hexagonal lattices
3. Serombehandlung mit einem langsam vernetzenden Fibrinkleber
4. Zweifache Uterusperforation bei disloziertem Silber-IUD
5. Metachrones Auftreten eines Mammakarzinoms, Ovarialkarzinoms und malignen Melanoms
6. EVALUATION OF THE IMPACT OF RADIAL GRADIENT OF NEUTRON SOURCE IN VVER NEUTRON FLUENCE CALCULATION
7. Improved coarse-mesh method for neutron diffusion calculations in hexagonal-z geometry / Verbesserte Grobgittermethode für Neutronendiffusionsrechnungen in hexagonal-z-Geometrie
8. Testing of Multigroup Neutron Cross-Section Libraries on Neutron Transmission Through the VVER-440 Vessel
9. Experimental assessment of neutron fluence for the Kozloduy Unit 1 pressure vessel by scraps and cavity dosimetry
10. Validation of Neutron Fluence Calculation Methodology for VVER-440 Vessel
11. A hexagonal diffusion theory burnup model for fast breeder reactor core design studies / Ein diffusionstheoretisches Abbrandmodell in hexagonaler Geometrie für Projektstudien an Kernen schneller Brutreaktoren.
12. The HEXAB-3D Three-Dimensional Few-Group Improved Coarse-Mesh Diffusion Code for Hexagonal-z Geometry
13. Experimental assessment of neutron fluence for the Kozloduy Unit I pressure vessel by scraps and cavity dosimetry
14. Comparative analysis of WWER-1000 benchmark calculations and improvements in hexagonal-Z diffusion methodology
15. Calculation results from radiation embrittlement of VVER pressure vessel at Kozloduy NPP
16. Verification of the VVER-440 pressure vessel neutron fluence calculation by activity measurement
17. An effective solution scheme of a three-dimensional reactor core model in hexagonal geometry
18. DIFFERENTIAL CALORIMETRIC METHOD FOR MEASURING ABSOLUTE ENERGY DOSES ABSORBED BY SUBSTANCES IN A MIXED REACTOR FIELD.
19. Three group investigation of space and energy distributions of reactor neutrons at their penetration through iron and lead neutron guides
20. Three-group investigation of space and energy distributions of reactor neutrons penetrating through iron and lead neutron guides
21. FOUR-GROUP INTEGRAL ALGORITHM FOR CALCULATION OF CRITICALITY OF HETEROGENEOUS URANIUM-WATER REACTORS.
22. Four-group physical scheme of burnup in uniform heterogeneous uranium-water reactors
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