Integral neutronic quantities have 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 lithium, beryllium, lead and thorium. The study covers the calculation of the integral tritium breeding ratio, the U-233 breeding rate (when applicable), the neutron multiplication ratio through (n,x)- and fission-(when applicable) reactions, and the heat release in those mixtures which are composed when first thorium is mixed with natural lithium or Li-6 for a volume fraction from 0% to 100% and then the variable thorium-lithium composition is mixed with Be or Pb for a volume fraction from 0% to 100%. (C) 1998 Elsevier Science Ltd. All rights...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
A plan of an advanced fusion neutron source (A-FNS) by using d-Li reaction is in progress at Rokkash...
The fissile breeding capability of a (D,T) fusion-fission (hybrid) reactor fueled with thorium is an...
Integral neutronic quantities have been evaluated for incident 14.1 MeV (D,T) and 2.45 MeV (D,D) fus...
Integral neutronic data has been evaluated for incident 14.1-MeV (D,T) fusion source neutrons in inf...
Integral neutronic data has been evaluated for incident 14.1-MeV (D,T) and 2.45 MeV (D,D) fusion sou...
The physical behavior of integral data in an infinite medium has been evaluated for incident fusion ...
For studying neutronic and nuclear characteristics of the projected International Fusion Materials I...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
WOS: 000088321800004The fissile breeding capability of a catalyzed-(D,D) and (D,T) fusion-fission (h...
Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since t...
At the present state of engineering development, the most probable fusion reactor fuel cycle will us...
This study presents the effects of mixture fractions of nuclear fuels ( mixture of fissile - fertile...
Achieving the economically viable release of energy by the fusion process has proved a major scienti...
The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
A plan of an advanced fusion neutron source (A-FNS) by using d-Li reaction is in progress at Rokkash...
The fissile breeding capability of a (D,T) fusion-fission (hybrid) reactor fueled with thorium is an...
Integral neutronic quantities have been evaluated for incident 14.1 MeV (D,T) and 2.45 MeV (D,D) fus...
Integral neutronic data has been evaluated for incident 14.1-MeV (D,T) fusion source neutrons in inf...
Integral neutronic data has been evaluated for incident 14.1-MeV (D,T) and 2.45 MeV (D,D) fusion sou...
The physical behavior of integral data in an infinite medium has been evaluated for incident fusion ...
For studying neutronic and nuclear characteristics of the projected International Fusion Materials I...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
WOS: 000088321800004The fissile breeding capability of a catalyzed-(D,D) and (D,T) fusion-fission (h...
Any fusion reactor in the near future will be based on the deuteriumtritium fusion reaction. Since t...
At the present state of engineering development, the most probable fusion reactor fuel cycle will us...
This study presents the effects of mixture fractions of nuclear fuels ( mixture of fissile - fertile...
Achieving the economically viable release of energy by the fusion process has proved a major scienti...
The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
A plan of an advanced fusion neutron source (A-FNS) by using d-Li reaction is in progress at Rokkash...
The fissile breeding capability of a (D,T) fusion-fission (hybrid) reactor fueled with thorium is an...