Start-up physics test predictions for Indian Point 3, cycle 7, utilized PHOENIX-P/ANC

Conference · Wed Nov 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5486960

Powers, M A ^[1]; Buechel, R J

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1. New York Power Authority, White Plains (USA)

The Westinghouse Advanced In-Core Fuel Management System (PHOENIX-P/ANC) was utilized to predict start-up physics test parameters for Indian Point 3 (IP3) cycle 7. This core utilizes a low-leakage loading pattern implementing VANTAGE-5 fuel, which incorporates axial blankets and integral fuel burnable absorbers. Discrete part-length wet annular burnable absorbers (WABAs) are used in some feed assemblies as well. As a measure to reduce vessel fluence, certain peripheral twice-burned assemblies also contain fresh full-length WABAs. The New York Power Authority (NYPA) is using the Westinghouse code system since the methodology was licensed by the U.S. Nuclear Regulatory Commission and because of the user support supplied by Westinghouse. The IP3 cycle 7 PHOENIX-P/ANC model was developed as a joint effort by NYPA and Westinghouse as part of a technology transfer agreement. The PHOENIX-P/ANC model performed very well in start-up physics test predictions and is expected to agree well through cycle depletion. These results have given NYPA further incentive to use the Westinghouse methodology for core follow, loading pattern design determination, and in the safety analysis area.

• OSTI ID: 5486960
• Report Number(s): CONF-891103--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 60
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BURNABLE POISONS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
FUEL MANAGEMENT
GROUP THEORY
INDIAN POINT-3 REACTOR
LICENSING
MATERIALS
MATHEMATICS
NATIONAL ORGANIZATIONS
NEUTRON ABSORBERS
NEUTRON FLUX
NUCLEAR DATA COLLECTIONS
NUCLEAR POISONS
OPERATION
P CODES
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR LICENSING
REACTOR MATERIALS
REACTOR OPERATION
REACTOR PHYSICS
REACTOR START-UP
REACTORS
SIMULATION
START-UP
TECHNOLOGY TRANSFER
THREE-DIMENSIONAL CALCULATIONS
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US ORGANIZATIONS
WATER COOLED REACTORS
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