FASTER test reactor preconceptual design report summary

Grandy, C.¹  Belch, H.¹  Brunett, A.¹  Heidet, F.¹  Hill, R.¹  Hoffman, E.¹  Jin, E.¹  Mohamed, W.¹  Moisseytsev, A.¹  Passerini, S.¹  Sienicki, J.¹  Sumner, T.¹  Vilim, R.¹  Hayes, Steven¹ 

[1] Argonne National Lab. (ANL), Argonne, IL (United States)

关键词: TEST REACTORS;    THERMAL NEUTRONS;    FAST NEUTRONS;    FAST REACTORS;    SODIUM COOLED REACTORS;    OPERATING COST;    DESIGN;    COST RECOVERY;    POWER RANGE 100-1000 MW;    ELECTRIC POWER;    POWER GENERATION;   

DOI  :  10.2172/1246340
RP-ID  :  ANL--ART-40
PID  :  OSTI ID: 1246340
Others  :  Other: 124963
Others  :  TRN: US1601252

美国|英语

来源: SciTech Connect

【 摘 要 】

The FASTER reactor plant is a sodium-cooled fast spectrum test reactor that provides high levels of fast and thermal neutron flux for scientific research and development. The 120MWe FASTER reactor plant has a superheated steam power conversion system which provides electrical power to a local grid allowing for recovery of operating costs for the reactor plant.