Sodium void reactivity comparison for advanced liquid-metal reactor fuels
- 1. Westinghouse Hanford Co., Richland, WA (United States)
Description
The advanced liquid-metal reactor (ALMR) program in the US is based on metal as the reference fuel because of its favorable neutronic feedback characteristics for passive safety. Favorable relationships exist between core performance and safety that provide a passively safe metal fuel system with a large margin to sodium boiling. Because of this, the reduction of the positive sodium void coefficient of reactivity is not an overriding design objective. A positive sodium void effect with metal fuel is due to neutron spectral hardening that dominates capture and leakage changes during sodium voiding. This can produce as much as 5-$ positive sodium void reactivity for mixed plutonium-uranium fuel in a smaller core designed for a near-zero burnup reactivity swing. It is possible to reduce the positive void feedback and its effect on hypothetical loss-of-flow (LOF) scenarios with a commensurate increase in burnup swing. However, metal fuel's small Doppler coefficient, excellent fuel conductivity, and resultant small temperature gradients provide less reactivity feedback to handle postulated transient overpower (TOP) events for cores with significant burnup reactivity swings. The purpose of this work was to study the relationship between reduction of the sodium void and the resultant increase in the burnup reactivity swing for an ALMR modeled with metal, nitride, and oxide fuel
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 319-320
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 2-6 Jun 1991.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036862
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY NUCLEAR FUELS; BURNUP; COMPARATIVE EVALUATIONS; DESIGN; DOPPLER EFFECT; LIQUID METAL COOLED REACTORS; LOSS OF FLOW; MIXED NITRIDE FUELS; MIXED OXIDE FUELS; NUCLEAR DATA COLLECTIONS; REACTIVITY; REACTOR CORES; REACTOR KINETICS; REACTOR SAFETY; TRANSIENT OVERPOWER ACCIDENTS; USA; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; DEVELOPED COUNTRIES; ENERGY SOURCES; EVALUATION; FUELS; KINETICS; MATERIALS; NORTH AMERICA; NUCLEAR FUELS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SAFETY; SOLID FUELS
Optional Information
- Secondary number(s)
- CONF-910603--.