A semianalytic two-group nodal model for SIMULATE-3

Conference · Fri Jan 01 04:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5818721

Esser, P D; Smith, K S ^[1]

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1. Studsvik of America, Idaho Falls, ID (United States)

Light water reactor (LWR) cores containing highly enriched ([ge] 10% Pu) mixed-oxide (MOX) fuel exhibit steep thermal flux gradients near MOX-UO[sub 2] assembly interfaces. The fourth-order polynomial representation of the internodal flux used in many polynomial nodal methods (including the QPANDA nodal model in the SIMULATE-3 core analysis code) has already been verified against low-enriched MOX fuel but cannot accurately portray the severe flux variations near highly enriched MOX interfaces. This paper describes the development of an enhanced nodal model that includes transcendental components in the thermal flux profile.

• OSTI ID: 5818721
• Report Number(s): CONF-930601--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 68
• Country of Publication: United States
• Language: English

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