The physical behavior of integral data in an infinite medium has been evaluated for incident fusion neutrons with the help of the 3-D Monte Carlo Code. In a fusion reactor blanket with finite dimension, the integral quantities will be more or less different from the infinite medium results, depending on the neutron leakage fraction. Design studies foresee reduction of the neutron leakage out of the blanket to very low levels in order to prevent nuclear heating in superconducting fusion magnets and to keep all neutrons primarily in the coolant. The most important materials in fusion technology, namely tritium, beryllium, lead, and uranium have been investigated in an infinitive medium
This study gives a report an neutronic calculations which have been performed to design the blanket ...
Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since t...
In this work the modern evaluated nuclear data for structural materials such as Fe, Cr, Ni are consi...
Integral neutronic data has been evaluated for incident 14.1-MeV (D,T) and 2.45 MeV (D,D) fusion sou...
Integral neutronic data has been evaluated for incident 14.1-MeV (D,T) fusion source neutrons in inf...
Integral neutronic quantities have been evaluated for incident 14.1 MeV (D,T) and 2.45 MeV (D,D) fus...
This study presents the neutronic behavior of integral data in an infinite target medium driven by a...
Integral physics data for fast reactor design are discussed. The measurements needed include those o...
In the framework of the EFF (European fusion file) - project of the European Fusion Technology Progr...
Cross-sections nuclear data are invaluable to the nuclear community. As well as providing informatio...
Achieving the economically viable release of energy by the fusion process has proved a major scienti...
Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among...
Any fusion reactor using tritium-deuterium fusion will be a prolific source of 14 MeV neutrons. In f...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel ...
This study gives a report an neutronic calculations which have been performed to design the blanket ...
Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since t...
In this work the modern evaluated nuclear data for structural materials such as Fe, Cr, Ni are consi...
Integral neutronic data has been evaluated for incident 14.1-MeV (D,T) and 2.45 MeV (D,D) fusion sou...
Integral neutronic data has been evaluated for incident 14.1-MeV (D,T) fusion source neutrons in inf...
Integral neutronic quantities have been evaluated for incident 14.1 MeV (D,T) and 2.45 MeV (D,D) fus...
This study presents the neutronic behavior of integral data in an infinite target medium driven by a...
Integral physics data for fast reactor design are discussed. The measurements needed include those o...
In the framework of the EFF (European fusion file) - project of the European Fusion Technology Progr...
Cross-sections nuclear data are invaluable to the nuclear community. As well as providing informatio...
Achieving the economically viable release of energy by the fusion process has proved a major scienti...
Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among...
Any fusion reactor using tritium-deuterium fusion will be a prolific source of 14 MeV neutrons. In f...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel ...
This study gives a report an neutronic calculations which have been performed to design the blanket ...
Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since t...
In this work the modern evaluated nuclear data for structural materials such as Fe, Cr, Ni are consi...