Add to ORKGIntegral neutronic data has been evaluated for incident 14.1-MeV (D,T) and 2.45 MeV (D,D) fusion source neutrons in infinite medium for the most important materials in fusion technology, namely for lithium, beryllium, lead, and thorium. The study covers the calculation of the integral tritium breeding ratio (TBR), U-233 breeding rate (when applicable), neutron multiplication rate through (n,x)- and fission- (when applicable) reactions and the heat release
Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since t...
In the present work the neutron emission spectra from a graphite cube, and from natural uranium, lit...
At the present state of engineering development, the most probable fusion reactor fuel cycle will us...
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...
The physical behavior of integral data in an infinite medium has been evaluated for incident fusion ...
Achieving the economically viable release of energy by the fusion process has proved a major scienti...
In the framework of the EFF (European fusion file) - project of the European Fusion Technology Progr...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
For studying neutronic and nuclear characteristics of the projected International Fusion Materials I...
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...
Cross-sections nuclear data are invaluable to the nuclear community. As well as providing informatio...
To validate nuclear data and code in the neutronics design of a hybrid reactor with thorium, integra...
The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage ...
Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since t...
In the present work the neutron emission spectra from a graphite cube, and from natural uranium, lit...
At the present state of engineering development, the most probable fusion reactor fuel cycle will us...
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...
The physical behavior of integral data in an infinite medium has been evaluated for incident fusion ...
Achieving the economically viable release of energy by the fusion process has proved a major scienti...
In the framework of the EFF (European fusion file) - project of the European Fusion Technology Progr...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
For studying neutronic and nuclear characteristics of the projected International Fusion Materials I...
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...
Cross-sections nuclear data are invaluable to the nuclear community. As well as providing informatio...
To validate nuclear data and code in the neutronics design of a hybrid reactor with thorium, integra...
The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage ...
Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since t...
In the present work the neutron emission spectra from a graphite cube, and from natural uranium, lit...
At the present state of engineering development, the most probable fusion reactor fuel cycle will us...