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Benchmark of the Westinghouse PHOENIX-P/ANC computer codes

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:6843681
Core designs currently performed by Commonwealth Edison (Edison) utilize a two-dimensional (x-y) fine-mesh neutron diffusion code that was converted from the Westinghouse TURTLE code. Due to the recent implementation of the Westinghouse VANTAGE 5 fuel assembly, which features axial blanket and part-length burnable absorbs in the Byron, Braidwood, and Zion nuclear reactors, and the plan to use part-length hafnium absorber rods to reduce the Zion reactor vessel fluence due to pressurized thermal shock concerns, it became necessary to model the reactor core in three dimensions. The advanced nodal code (ANC) developed by Westinghouse was obtained by Edison and a benchmark program performed to compare the calculated results to measured data and vendor calculations. The benchmark program consisted of comparisons of predicted data to measured results for two reload cycles (Byron unit 1 cycle 4 and Zion unit 1 cycle 11) and comparison to vendor results for one reload cycle (Braidwood unit 2 cycle 2). The parameters selected for comparison were critical boron concentrations, rod worths, isothermal temperature coefficient, power distribution, delayed neutron fraction and the rod ejection analysis. Only the results of the first three parameters are presented in this paper.
OSTI ID:
6843681
Report Number(s):
CONF-901101--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
Country of Publication:
United States
Language:
English

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FUEL ASSEMBLIES
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HADRONS
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NEUTRON ABSORBERS
NEUTRON DIFFUSION EQUATION
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OPERATION
P CODES
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REACTOR CORES
REACTOR KINETICS
REACTOR MATERIALS
REACTOR OPERATION
REACTOR PHYSICS
REACTOR SAFETY
REACTOR START-UP
REACTORS
ROD EJECTION ACCIDENTS
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T CODES
THERMAL REACTORS
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THREE-DIMENSIONAL CALCULATIONS
TRANSITION ELEMENTS
TWO-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
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ZION-1 REACTOR