The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GGBR), and deuterium- moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site. The maximum annual fuel yields were 1.5 mills/ kwhr. The minimum estimated fuel cycle costs were 0.9, 0.6, 1.0, 1.2, and 1.3 mills/kwhr at fuel yields of were 0.9, 0.9, 1.5, 1.5, and 1.3 mills/kwhr. Only the AHBR and the MSBR are capable of achieving fuel yields substantially in excess of 4%/yr, and therefore, in view of the uncertainties in nucl...
In this paper, a methodology for investigating the applicability of thorium based fuels in existing ...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
The fissile breeding capability of a (D,T) fusion-fission (hybrid) reactor fueled with thorium is an...
Under present technological and economic conditions, minimum fuel costs in thermal reactors are asso...
This paper is an attempt to assess and review the materials aspects of the thorium fuel cycle. It st...
This paper is an attempt to assess and review the materials aspects of the thorium fuel cycle. It st...
A comparative study of the capability of some of the existing power reactor designs to produce fissi...
BREEDING CAPABILITY OF URANIUM AND THORIUM FUEL CYCLES FOR WATER COOLED REACTORS. Nuclear energy has...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
The role that could be played by liquid metal-cooled fast breeder reactors (LMFBRs) in the utilizati...
Production of denaturated fissile fuel in a thorium fusion breeder has been investigated by mixing t...
Production of denaturated fissile fuel in a thorium fusion breeder has been investigated by mixing t...
The design and economics of the Aqueous Homogeneous Reactor as basically under development at the Oa...
In this paper, a reduced-moderation LWR (RMLWR) system is compared to a sodium-cooled fast reactor (...
In this paper, a methodology for investigating the applicability of thorium based fuels in existing ...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
The fissile breeding capability of a (D,T) fusion-fission (hybrid) reactor fueled with thorium is an...
Under present technological and economic conditions, minimum fuel costs in thermal reactors are asso...
This paper is an attempt to assess and review the materials aspects of the thorium fuel cycle. It st...
This paper is an attempt to assess and review the materials aspects of the thorium fuel cycle. It st...
A comparative study of the capability of some of the existing power reactor designs to produce fissi...
BREEDING CAPABILITY OF URANIUM AND THORIUM FUEL CYCLES FOR WATER COOLED REACTORS. Nuclear energy has...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
The role that could be played by liquid metal-cooled fast breeder reactors (LMFBRs) in the utilizati...
Production of denaturated fissile fuel in a thorium fusion breeder has been investigated by mixing t...
Production of denaturated fissile fuel in a thorium fusion breeder has been investigated by mixing t...
The design and economics of the Aqueous Homogeneous Reactor as basically under development at the Oa...
In this paper, a reduced-moderation LWR (RMLWR) system is compared to a sodium-cooled fast reactor (...
In this paper, a methodology for investigating the applicability of thorium based fuels in existing ...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
The fissile breeding capability of a (D,T) fusion-fission (hybrid) reactor fueled with thorium is an...