Development of small, fast reactor core designs using lead-based coolant
Description
A variety of small (100 MWe) fast reactor core designs are developed, these include compact configurations, long-lived (15-year fuel lifetime) cores, and derated, natural circulation designs. Trade studies are described which identify key core design issues for lead-based coolant systems. Performance parameters and reactivity feedback coefficients are compared for lead-bismuth eutectic (LBE) and sodium-cooled cores of consistent design. The results of these studies indicate that the superior neutron reflection capability of lead alloys reduces the enrichment and burnup swing compared to conventional sodium-cooled systems; however, the discharge fluence is significantly increased. The size requirement for long-lived systems is constrained by reactivity loss considerations, not fuel burnup or fluence limits. The derated lead-alloy cooled natural circulation cores require a core volume roughly eight times greater than conventional compact systems. In general, reactivity coefficients important for passive safety performance are less favorable for the larger, derated configurations
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00011847; PURL: https://www.osti.gov/servlets/purl/11847-t5SlGg/webviewable/Files
32065043.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- ANL/RA/CP--99218
Conference
- Title
- American Nuclear Society International Conference on Future Nuclear Systems
- Acronym
- Global '99
- Dates
- 29 Aug - 3 Sep 1999
- Place
- Jackson Hole, WY (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 32065043
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BISMUTH ALLOYS; COOLANTS; DESIGN; FAST REACTORS; LEAD ALLOYS; NATURAL CONVECTION; REACTIVITY COEFFICIENTS; REACTOR CORES; SODIUM
- Descriptors DEC
- ALKALI METALS; ALLOYS; CONVECTION; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; HEAT TRANSFER; MASS TRANSFER; METALS; REACTOR COMPONENTS; REACTORS
Optional Information
- Contract/Grant/Project number
- W-31109-ENG-38
- Funding organization
- US Department of Energy (United States)