Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since tritium cannot be found in sufficient quantities in nature, it has to be bred from neutron induced reactions on lithium; this lithium will surround the plasma volume. In order to make inquiries into the involved cross sections, a cylindricallithium blanket model was constructed; in this model a graphite or beryllium layer can also be applied. For a simulation of the fusion neutron source a D-T neutron generator is used. The space dependent neutron spectra and the tritium production for this model are determined experimentally with the aid of activation techniquesand radiochemical methods, respectively ; they are also calculated with a Monte Ca...
One of the major requirements for a fusion power plant in the future is tritium self-sufficiency. Fo...
AbstractHigh energy neutrons produced in future fusion reactors will cause significant transmutation...
Integral neutronic quantities have been evaluated for incident 14.1 MeV (D,T) and 2.45 MeV (D,D) fus...
At the present state of engineering development, the most probable fusion reactor fuel cycle will us...
This study gives a report an neutronic calculations which have been performed to design the blanket ...
The space dependent energy deposition and tritium production rate for a lithium-metal fusion reactor...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
In the framework of the development of a fusion reactor blanket the irradiation experiment TRIDEX ($...
For studying neutronic and nuclear characteristics of the projected International Fusion Materials I...
In the present work the neutron emission spectra from a graphite cube, and from natural uranium, lit...
In this work a method to collapse a 3D geometry into a mono dimensional model of a fusion reactor bl...
An experimental method for measuring the relative, space-dependent tritium production in a blanket m...
Typescript (photocopy).Numerical and experimental studies were carried out to assess the feasibility...
The viability of various materials and blanket designs for use in nuclear fusion reactors can be tes...
The project studies blanket designs of ITER and DEMO for neutron shielding, helium production and tr...
One of the major requirements for a fusion power plant in the future is tritium self-sufficiency. Fo...
AbstractHigh energy neutrons produced in future fusion reactors will cause significant transmutation...
Integral neutronic quantities have been evaluated for incident 14.1 MeV (D,T) and 2.45 MeV (D,D) fus...
At the present state of engineering development, the most probable fusion reactor fuel cycle will us...
This study gives a report an neutronic calculations which have been performed to design the blanket ...
The space dependent energy deposition and tritium production rate for a lithium-metal fusion reactor...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
In the framework of the development of a fusion reactor blanket the irradiation experiment TRIDEX ($...
For studying neutronic and nuclear characteristics of the projected International Fusion Materials I...
In the present work the neutron emission spectra from a graphite cube, and from natural uranium, lit...
In this work a method to collapse a 3D geometry into a mono dimensional model of a fusion reactor bl...
An experimental method for measuring the relative, space-dependent tritium production in a blanket m...
Typescript (photocopy).Numerical and experimental studies were carried out to assess the feasibility...
The viability of various materials and blanket designs for use in nuclear fusion reactors can be tes...
The project studies blanket designs of ITER and DEMO for neutron shielding, helium production and tr...
One of the major requirements for a fusion power plant in the future is tritium self-sufficiency. Fo...
AbstractHigh energy neutrons produced in future fusion reactors will cause significant transmutation...
Integral neutronic quantities have been evaluated for incident 14.1 MeV (D,T) and 2.45 MeV (D,D) fus...