Peak burnup prediction for an ATR uranium-aluminide fuel elements

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

OSTI ID:6911927

Kim, S S; Smith, A C; Judd, J L ^[1]

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1. Idaho National Engineering Lab., Idaho Falls, ID (United States)

The analytical two- and three-dimensional PDQ models for the Advanced Test Reactor (ATR) were developed to update the principal computing tool and to perform physics analysis for the final safety analysis report (FSAR) upgrade. The models were validated at the beginning of cycle, utilizing fresh fuel, through comparison with measured data from the ATR fission rate monitors. In the model, the time dependence of the nuclides is represented with two predominant uranium ([sup 235]U and [sup 238]U) and three major fission product ([sup 135]Xe, [sup 149]Sm, and lumped fission product) depletion chains accounting for fuel depletion in the core. The two-dimensional ATR core model has been depleted, as described in this paper, to predict the peak burnup of an ATR fuel element. The bench-marking of this model validates the analytical depletion model, providing valuable data for the assessment of the analytical full-core model.

• OSTI ID: 6911927
• Report Number(s): CONF-931160--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ATR REACTOR
BURNUP
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
IRRADIATION REACTORS
MATERIALS TESTING REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
SAFETY ANALYSIS
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS