Model development for plant Vogtle utilizing ALPHA/PHOENIX-P/ANC methodology
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6782346
The Westinghouse advanced in-core fuel management system (ALPHA/PHOENIX-P/ANC) has been utilized to generate models and predict start-up physics test parameters for the Vogtle units. The initial cores for each unit had an out-in loading pattern and used standard burnable absorbers. In cycle 2 of each unit, low-leakage loading patterns and wet annular burnable absorbers (WABAs) were implemented. Plans call for VANTAGE-5 fuel and integral fuel burnable absorbers (IFBAs) to be implemented in Vogtle 1 cycle 4 and Vogtle 2 cycle 3. Start-up results are discussed for the cycles for which start-up results and final models are now available. Southern Company Services (SCS) is using the Westinghouse code system because the methodology was licensed by the US Nuclear Regulatory Commission, and because of the user support supplied by Westinghouse. The Vogtle ALPHA/PHOENIX-P/ANC models were developed by SCS with Westinghouse oversight as part of a technology transfer agreement.
- OSTI ID:
- 6782346
- 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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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
A CODES
BURNABLE POISONS
COMPUTER CODES
ENRICHED URANIUM REACTORS
FUEL MANAGEMENT
IMPLEMENTATION
MATERIALS
MULTIGROUP THEORY
NATIONAL ORGANIZATIONS
NEUTRON ABSORBERS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUCLEAR POISONS
OPERATION
P CODES
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTOR OPERATION
REACTOR PHYSICS
REACTOR START-UP
REACTORS
START-UP
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
US NRC
US ORGANIZATIONS
VOGTLE-1 REACTOR
VOGTLE-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
A CODES
BURNABLE POISONS
COMPUTER CODES
ENRICHED URANIUM REACTORS
FUEL MANAGEMENT
IMPLEMENTATION
MATERIALS
MULTIGROUP THEORY
NATIONAL ORGANIZATIONS
NEUTRON ABSORBERS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUCLEAR POISONS
OPERATION
P CODES
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTOR OPERATION
REACTOR PHYSICS
REACTOR START-UP
REACTORS
START-UP
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
US NRC
US ORGANIZATIONS
VOGTLE-1 REACTOR
VOGTLE-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS