Thorium-based fuels in fast breeder reactors

Journal Article · Sat Oct 01 00:00:00 EDT 1977 · Nucl. Technol.; (United States)

OSTI ID:7209013

Sehgal, B R; Naser, J A; Lin, C L; Loewenstein, W B

A number of thorium-based fuels for fast breeder reactors using either sodium or helium coolant are considered. Thorium-plutonium mixed-oxide fuels have similar or slightly better material properties than those for mixed uranium-plutonium oxides. Their thermal performance is also very similar to that of the UO/sub 2/--PuO/sub 2/ mixed-oxide fuel. Their nuclear performance shows a substantially lower breeding gain, but a much lower positive sodium void coefficient than those for the UO/sub 2/--PuO/sub 2/ system. The material properties of Th-U-Pu and Th-U metal alloys are more suitable for reactor application than those of the uranium metal alloy. The Th-U-Pu metal alloy system has higher breeding gain, much lower positive sodium void coefficient, and a possibly higher negative Doppler coefficient of reactivity than the magnitude of those parameters for the UO/sub 2/--PuO/sub 2/ system. The Th-/sup 233/U metal alloy system has a slightly lower breeding gain than the UO/sub 2/--PuO/sub 2/ system, but it has a negative reactivity coefficient for sodium voiding from the core. Equilibrium fuel cycle calculations reveal that all of the thorium metal alloy systems have a longer cycle length than the UO/sub 2/--PuO/sub 2/ system for the same burnup constraint. Thermal-hydraulic calculations show that sodium-bonded thorium metal alloy fuel elements may be able to operate up to an approximate 82 kW/m (25 kW/ft) peak power rating in sodium coolant.

• Research Organization: Electric Power Research Inst., Palo Alto, CA
• OSTI ID: 7209013
• Journal Information: Nucl. Technol.; (United States), Vol. 35:3
• Country of Publication: United States
• Language: English

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PLANNING
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NUCLEAR FUELS
PERFORMANCE
THORIUM
ACTINIDES
BREEDER REACTORS
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Breeding