Comparative sodium void effects for different advanced liquid metal reactor fuel and core designs

Conference · Mon Jul 01 00:00:00 EDT 1991

OSTI ID:5435746

Dobbin, K D; Kessler, S F; Nelson, J V; Gedeon, S R; Omberg, R P

An analysis of metal-, oxide, and nitride-fueled advanced liquid metal reactor cores was performed to investigate the calculated differences in sodium void reactivity, and to determine the relationship between sodium void reactivity and burnup reactivity swing using the three fuel types. The results of this analysis indicate that nitride fuel has the least positive sodium void reactivity for any given burnup reactivity swing. Thus, it appears that a good design compromise between transient overpower and loss of flow response is obtained using nitride fuel. Additional studies were made to understand these and other nitride advantages. 8 refs., 5 figs., 3 tabs.

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 5435746
• Report Number(s): WHC-SA-1093; CONF-911001-5; ON: DE91017741
• Resource Relation: Conference: International conference on fast reactor systems and fuel cycles, Kyoto (Japan), 27 Oct - 1 Nov 1991
• Country of Publication: United States
• Language: English

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COMPARATIVE EVALUATIONS
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