Discrete rod burnup analysis capability in the Westinghouse advanced nodal code

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6966435

Buechel, R J; Fetterman, R J; Petrunyak, M A ^[1]

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1. Westinghouse Electric Corp., Pittsburgh, PA (United States)

Core design analysis in the last several years has evolved toward the adoption of nodal-based methods to replace traditional fine-mesh models as the standard neutronic tool for first core and reload design applications throughout the nuclear industry. The accuracy, speed, and reduction in computation requirements associated with the nodal methods have made three-dimensional modeling the preferred approach to obtain the most realistic core model. These methods incorporate detailed rod power reconstruction as well. Certain design applications such as confirmation of fuel rod design limits and fuel reconstitution considerations, for example, require knowledge of the rodwise burnup distribution to avoid unnecessary conservatism in design analyses. The Westinghouse Advanced Nodal Code (ANC) incorporates the capability to generate the intra-assembly pin burnup distribution using an efficient algorithm.

• OSTI ID: 6966435
• Report Number(s): CONF-920606--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
A CODES
ACCURACY
BURNUP
COMPUTER CODES
DESIGN
EFFICIENCY
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
MESH GENERATION
NODAL EXPANSION METHOD
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
REACTORS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS