682 results on '"uranium 233"'
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2. Measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U
3. Detailed Investigations of Neutron–Neutron Angular Correlations in Slow-Neutron-Induced Fission of {sup 233}U, {sup 235}U, and {sup 239}Pu
4. Physical particularities of nuclear reactors using heavy moderators of neutrons
5. On the role of fusion neutron source with thorium blanket in forming the nuclide composition of the nuclear fuel cycle of the Russian Federation
6. Simulation on reactor TRIGA Puspati core kinetics fueled with thorium (Th) based fuel element
7. Hybrid fusion–fission reactor with a thorium blanket: Its potential in the fuel cycle of nuclear reactors
8. The procedure and results of calculations of the equilibrium isotopic composition of a demonstration subcritical molten salt reactor
9. Breeding of {sup 233}U in the thorium–uranium fuel cycle in VVER reactors using heavy water
10. Utilization of non-weapons-grade plutonium and highly enriched uranium with breeding of the {sup 233}U isotope in the VVER reactors using thorium and heavy water
11. Multiple recycle of REMIX fuel at VVER-1000 operation in closed fuel cycle
12. Concept of a demonstrational hybrid reactor—a tokamak with molten-salt blanket for {sup 233}U fuel production: 1. Concept of a stationary Tokamak as a neutron source
13. Analysis of fluid fuel flow to the neutron kinetics on molten salt reactor FUJI-12
14. Optimization of small long-life PWR based on thorium fuel
15. Properties of true quaternary fission of nuclei with allowance for its multistep and sequential character
16. Current Issues in Nuclear Data Evaluation Methodology: {sup 235}U Prompt Fission Neutron Spectra and Multiplicity for Thermal Neutrons
17. Renewability and sustainability aspects of nuclear energy
18. Analysis on fuel breeding capability of FBR core region based on minor actinide recycling doping
19. Conceptual design study of small long-life PWR based on thorium cycle fuel
20. Effect of graphite properties in thermal analysis of CHTR: A parametric study
21. ORNL Resolved Resonance Covariance Generation for ENDF/B-VII.1
22. Fission-suppressed fusion breeder on the thorium cycle and nonproliferation
23. Design study of Thorium-232 and Protactinium-231 based fuel for long life BWR
24. Plutonium and minor actinides utilization in Thorium molten salt reactor
25. Design study of long-life PWR using thorium cycle
26. Preliminary results of calculations for heavy-water nuclear-power-plant reactors employing {sup 235}U, {sup 233}U, and {sup 232}Th as a fuel and meeting requirements of a nonproliferation of nuclear weapons
27. Short-lived fission product measurements from >0.1 MeV neutron-induced fission using boron carbide.
28. Probing Nilsson states in {sup 233}U
29. Actinide Neutron-Induced Fission Cross Section Measurements At LANSCE
30. Ingot Niobium RF Cavity Design and Development at BARC
31. Neutron-induced fission cross-section of 233U in the energy range 0.5<En<20 MeV
32. Fuel Breeding and Core Behavior Analyses on In Core Fuel Management of Water Cooled Thorium Reactors
33. Fission Product Yields of {sup 233}U, {sup 235}U, {sup 238}U and {sup 239}Pu in Fields of Thermal Neutrons, Fission Neutrons and 14.7-MeV Neutrons
34. Study of Neutron-Induced Fission Cross Sections of U, Am, and Cm at n{sub T}OF
35. Determination of neutron multiplication coefficients for fuel elements irradiated by spallation neutrons
36. High-accuracy {sup 233}U(n,f) cross-section measurement at the white-neutron source n{sub T}OF from near-thermal to 1 MeV neutron energy
37. Half-life estimation of the first excited state of {sup 229}Th by using {alpha}-particle spectrometry
38. Surrogate ratio method in the actinide region using the ({alpha},{alpha}{sup '}f) reaction
39. Neutron capture by fissile and fertile actinide targets
40. Isomers in Fission Fragments
41. Processing Neutron Cross Section Covariances using NJOY-99 and PUFF-IV
42. Resonance Region Covariance Analysis Method and New Covariance Data for {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, and {sup 239}Pu
43. Current Inconsistencies in {sup 238}Pu, {sup 241,243}Am and {sup 242}Cm Evaluations and their Impact on Uncertainties
44. Nuclear Data Sheets for A = 229
45. Evaluation of Neutron Reactions for ENDF/B-VII: {sup 232-241}U and {sup 239}Pu
46. Measurement of the electric hyperfine coupling constant P/k in a uranyl rubidium nitrate crystal
47. Measurement of the Neutron Induced Fission Cross Section on Transuranic (TRU) Elements at the n lowbar TOF Facility at CERN
48. Energy Splitting of the Ground-State Doublet in the Nucleus {sup 229}Th
49. Determining (n,f) cross sections for actinide nuclei indirectly: Examination of the surrogate ratio method
50. Energy dependence of proton induced fission cross sections for heavy nuclei in the energy range 200-1000 MeV
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