Loading of seedless thoria rods in internal blanket regions and using them later as part of seeded fuel assemblies is the central theme of the thorium breeder reactor (ATBR) concept [1]. The fast reactors presently consider seedless blanket region surrounding the seeded core region. This results in slower fissile production rate in comparison to fissile depletion rate per unit volume. The overall breeding is achieved mainly by employing blanket core with more than double the volume of seeded core. The blanket fuel is discharged with fissile content of ∼30g/kg, which is much less than the asymptotic maximum possible fissile content of 100g/kg. This is due to smaller coolant flow provided for in the blanket regions. In a newly proposed fast thorium breeder reactor (FTBR) [2], the blanket region is brought in and distributed through out the core. By this the fissile depletion and production rates per unit volume become comparable. The core considered simultaneous breeding from both fertile thoria and depleted uranium and hence the concept can be called as fast twin breeder reactor as well. Sodium is used as coolant. The blanket fuel rods achieve nearly 80% of the seed fuel rod burnup and also contain nearly the maximum possible fissile content at the time of discharge. In this paper a comparison of FTBR core characteristics with oxide and metallic fuel are compared.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4814-0
PROCEEDINGS PAPER
A Comparison of Fast Thorium Breeder Reactor Designs With Oxide and Metallic Fuels
V. Jagannathan,
V. Jagannathan
Bhabha Atomic Research Centre, Mumbai, India
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Usha Pal,
Usha Pal
Bhabha Atomic Research Centre, Mumbai, India
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R. Karthikeyan,
R. Karthikeyan
Bhabha Atomic Research Centre, Mumbai, India
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Devesh Raj
Devesh Raj
Bhabha Atomic Research Centre, Mumbai, India
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V. Jagannathan
Bhabha Atomic Research Centre, Mumbai, India
Usha Pal
Bhabha Atomic Research Centre, Mumbai, India
R. Karthikeyan
Bhabha Atomic Research Centre, Mumbai, India
Devesh Raj
Bhabha Atomic Research Centre, Mumbai, India
Paper No:
ICONE16-48679, pp. 865-881; 17 pages
Published Online:
June 24, 2009
Citation
Jagannathan, V, Pal, U, Karthikeyan, R, & Raj, D. "A Comparison of Fast Thorium Breeder Reactor Designs With Oxide and Metallic Fuels." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. Orlando, Florida, USA. May 11–15, 2008. pp. 865-881. ASME. https://doi.org/10.1115/ICONE16-48679
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