A fuel cycle economic study has been made for a 315Mwe graphite- moderated slightly enriched fused-salt reactor. Fuel cycle costs of less than 1.5 mills may be possible for such reactors operating on a ten-year cycle even when the fuel is discarded at the end of the cycle. Recovery of the uranium and plutonium at the end of the cycle reduces the fuel cycle costs to approximates 1 mill/kwh. Changes in the waste storage cost, reprocessing cost or salt inventory have a relatively minor effect on fuel cycle costs. (auth
This paper proposes a concept of molten salt fast reactor (MSFR) using chloride salts and U/Pu cycle...
International audienceThis paper proposes a concept of molten salt fast reactor (MSFR) using chlorid...
As the global need for low carbon energy sources increases exponentially, nuclear power plants are c...
A fuel-cycle economic study was made for a 315-Mw(e) graphite-moderated U/sup 235/-Th-fueled fused-s...
The costs of the chemical and metallurgical steps in the fuel cycle for large desalination reactors ...
A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, ...
A study was made to determine the effect of changes in natural uranium cost and in separative work c...
As part of its charter, the Alternate Fuel Cycle Evaluation Program (AFCEP) was directed to evaluate...
By using a large central fuel-and-blanket processing facility, slurry- fueled aqueous homogeneous re...
A rough survey of the nuclear charactenistics of graphite-moderated molten-salt reactors utilizing a...
An economic analysis has been performed to compare four nuclear fuel cycle options: a once-through c...
The total electric generating costs at the power plant busbar are estimated for various nuclear reac...
A design study is presented for a sodium cooled, graphite moderated power reactor utilizing low enri...
A study was made to examine the conceptual feasibility of a molten-salt power reactor fueled with de...
The use of beryllium oxide as a moderator in a high temperature gas-cooled pebble bed reactor system...
This paper proposes a concept of molten salt fast reactor (MSFR) using chloride salts and U/Pu cycle...
International audienceThis paper proposes a concept of molten salt fast reactor (MSFR) using chlorid...
As the global need for low carbon energy sources increases exponentially, nuclear power plants are c...
A fuel-cycle economic study was made for a 315-Mw(e) graphite-moderated U/sup 235/-Th-fueled fused-s...
The costs of the chemical and metallurgical steps in the fuel cycle for large desalination reactors ...
A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, ...
A study was made to determine the effect of changes in natural uranium cost and in separative work c...
As part of its charter, the Alternate Fuel Cycle Evaluation Program (AFCEP) was directed to evaluate...
By using a large central fuel-and-blanket processing facility, slurry- fueled aqueous homogeneous re...
A rough survey of the nuclear charactenistics of graphite-moderated molten-salt reactors utilizing a...
An economic analysis has been performed to compare four nuclear fuel cycle options: a once-through c...
The total electric generating costs at the power plant busbar are estimated for various nuclear reac...
A design study is presented for a sodium cooled, graphite moderated power reactor utilizing low enri...
A study was made to examine the conceptual feasibility of a molten-salt power reactor fueled with de...
The use of beryllium oxide as a moderator in a high temperature gas-cooled pebble bed reactor system...
This paper proposes a concept of molten salt fast reactor (MSFR) using chloride salts and U/Pu cycle...
International audienceThis paper proposes a concept of molten salt fast reactor (MSFR) using chlorid...
As the global need for low carbon energy sources increases exponentially, nuclear power plants are c...