Published June 11, 1999 | Version v1
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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/

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Additional details

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)