AbstractExperimental Breeder Reactor – II (EBR-II) metallic fuel was qualified for high burnup to approximately 10 atomic per cent. Subsequently, the electrometallurgical treatment of this fuel was demonstrated. Advanced metallic fuels are now investigated for increased performance, including ultra-high burnup and actinide burning. Advances include additives to mitigate the fuel/cladding chemical interaction and uranium alloys that combine Mo, Ti and Zr to improve alloy performance. The impacts of the advances—on fabrication, waste streams, electrorefining, etc.—are found to be minimal and beneficial. Owing to extensive research literature and computational methods, only a modest effort is required to complete their development
Argonne National Laboratory has refurbished and equipped an existing hot cell facility for demonstra...
Following the successful demonstration of electrometallurgical treatment, the Spent Fuel Treatment P...
AbstractMetal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PG...
Experimental Breeder Reactor – II (EBR-II) metallic fuel was qualified for high burnup to approximat...
AbstractExperimental Breeder Reactor – II (EBR-II) metallic fuel was qualified for high burnup to ap...
Argonne National Laboratory has been working for the past five years to develop and demonstrate the ...
The application of electrometallurgical technology to spent nuclear fuel treatment is being demonstr...
Next generation fast reactor designs utilizing metallic fuel are being developed as an alternative f...
Several recent advances have been achieved for the electrometallurgical treatment of spent nuclear f...
Higher breeding ratio, high thermal conductivity, shorter doubling time and high plutonium productio...
The Experimental Breeder Reactor-II (EBR-II) was a 62.5 MWt–20 MWe sodium cooled fast reactor that w...
Advanced Water Reactor Program. The second fuel loading for the EBWR is planned as ThO/sub 2/--UO/su...
Metallic fuels are proposed for use in advanced sodium cooled fast reactors. The experience basis fo...
A worldwide objective in nuclear energy industry is the reduction of long-lived radio toxicity and h...
The proposed AFC-2A and AFC-2B irradiation experiments are a continuation of the metallic fuel test ...
Argonne National Laboratory has refurbished and equipped an existing hot cell facility for demonstra...
Following the successful demonstration of electrometallurgical treatment, the Spent Fuel Treatment P...
AbstractMetal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PG...
Experimental Breeder Reactor – II (EBR-II) metallic fuel was qualified for high burnup to approximat...
AbstractExperimental Breeder Reactor – II (EBR-II) metallic fuel was qualified for high burnup to ap...
Argonne National Laboratory has been working for the past five years to develop and demonstrate the ...
The application of electrometallurgical technology to spent nuclear fuel treatment is being demonstr...
Next generation fast reactor designs utilizing metallic fuel are being developed as an alternative f...
Several recent advances have been achieved for the electrometallurgical treatment of spent nuclear f...
Higher breeding ratio, high thermal conductivity, shorter doubling time and high plutonium productio...
The Experimental Breeder Reactor-II (EBR-II) was a 62.5 MWt–20 MWe sodium cooled fast reactor that w...
Advanced Water Reactor Program. The second fuel loading for the EBWR is planned as ThO/sub 2/--UO/su...
Metallic fuels are proposed for use in advanced sodium cooled fast reactors. The experience basis fo...
A worldwide objective in nuclear energy industry is the reduction of long-lived radio toxicity and h...
The proposed AFC-2A and AFC-2B irradiation experiments are a continuation of the metallic fuel test ...
Argonne National Laboratory has refurbished and equipped an existing hot cell facility for demonstra...
Following the successful demonstration of electrometallurgical treatment, the Spent Fuel Treatment P...
AbstractMetal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PG...