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Title: The Industrial Sodium Cooled Fast Reactor

Conference ·
OSTI ID:968556

This paper investigates the use of enrichment and moderator zoning methods for optimizing the r-z power distribution within sodium cooled fast reactors. These methods allow overall greater fuel utilization in the core resulting in more fuel being irradiated near the maximum allowed thermal power. The peak-to-average power density was held to 1.18. This core design, in conjunction with a multiple-reheat Brayton power conversion system, has merit for producing an industrial level of electrical output (2400MWth, 1000MWe) from a relatively compact core size. The total core radius, including reflectors and shields, was held to 1.78m. Preliminary safety analysis suggests that positive reactivity insertion resulting from a leak between the sodium primary loop and helium power conversion system can be mitigated using simple gas-liquid centripetal separation strategies in the plant’s primary loop.

Research Organization:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
DE-AC07-05ID14517
OSTI ID:
968556
Report Number(s):
INL/CON-09-15519; TRN: US0904704
Resource Relation:
Conference: Advances in Nuclear Fuel Management IV,Hilton Head, South Carolina,04/12/2009,04/15/2009
Country of Publication:
United States
Language:
English