Development of small, fast reactor core designs using lead-based coolant.

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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 ... continued below

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10 p.

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Cahalan, J. E.; Hill, R. N.; Khalil, H. S. & Wade, D. C. June 11, 1999.

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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.

Physical Description

10 p.

Notes

INIS; OSTI as DE00011847

Medium: P; Size: 10 pages

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  • GLOBAL '99 International Conference on Future Nuclear Systems, Jackson Hole, WY (US), 08/30/1999--09/02/1999

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  • Report No.: ANL/RA/CP-99218
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11847
  • Archival Resource Key: ark:/67531/metadc618434

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  • June 11, 1999

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  • June 16, 2015, 7:43 a.m.

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  • April 6, 2017, 6:42 p.m.

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Cahalan, J. E.; Hill, R. N.; Khalil, H. S. & Wade, D. C. Development of small, fast reactor core designs using lead-based coolant., article, June 11, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc618434/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.