Flux flattening in a graphite moderated core

Conference · Wed Nov 12 04:00:00 EST 1986

OSTI ID:7145267

Burnside, R J; Skeen, D R; Finfrock, S H; Robinson, A H; Toffer, H

An axial flux flattening program was instituted at N Reactor to lower the peak to average flux from 1.45 to the 1.25-1.30 range. Axially varying fuel enrichments are being used to accomplish the reduced peaking. The flux flattening program objectives are to improve operational constraints, safety margins, nuclear material production, and to homogenize fluence impacts upon the graphite moderator for the rest of the reactor's life. Development of numerical methods and computer models to provide design information was key to the program's success.

• Research Organization: UNC Nuclear Industries, Inc., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01857
• OSTI ID: 7145267
• Report Number(s): UNI-SA-179; CONF-861102-26; ON: DE87002689
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ENRICHED URANIUM REACTORS
GRAPHITE MODERATED REACTORS
LWGR TYPE REACTORS
N-REACTOR
NEUTRON FLUX FLATTENING
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
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WATER COOLED REACTORS