Experiences with PHOENIX-P/ANC Modeling at the South Texas Project
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:6934571
Houston Lighting and Power (HL and P) has implemented the advanced nodal methodology in its reactor physics models by the use of the PHOENIX-P/ANC code system from the Westinghouse Electric Corporation. This code system replaced the CASMO-2E/PDQ-7E/SIMULATE-E system available from Studsvik and the Electric Power Research Institute (EPRI). The manpower requirements for both training and model construction using PHOENIX-P/ANC has been found to be significantly less than that for the previous code system. Beyond the training provided by Westinghouse, only a limited amount of methodology development has been done at HL and P. However, the model predictions compare favorably with plant measurements. The predictions of labor and computer savings by moving to the use of the advanced nodal methodology have been shown to be well founded. Since a PDQ model is not needed for pin-power calculations, considerable resources are saved. The relative ease of making the transition to the use of the advanced nodal methodology is a strong incentive to take advantage of the potential cost savings offered by this technology.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 6934571
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society 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
97 MATHEMATICS AND COMPUTING
A CODES
BORON
C CODES
CALCULATION METHODS
CASMO-2E/PDQ-7E/SIMULATE-E System
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
EDUCATION
ELECTRIC UTILITIES
ELEMENTS
ENRICHED URANIUM REACTORS
EPRI
Electric Power Research Institute (EPRI)
Houston Lighting and Power (HL and P)
MANPOWER
NODAL EXPANSION METHOD
Nuclear Criticality Safety Program (NCSP)
P CODES
PDQ
PHOENIX-P/ANC code
PHYSICS
POWER DENSITY
POWER REACTORS
PUBLIC UTILITIES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
REACTORS
S CODES
SEMIMETALS
SIMULATION
SOUTH TEXAS PROJECT-1 REACTOR
SOUTH TEXAS PROJECT-2 REACTOR
THERMAL REACTORS
TRAINING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
97 MATHEMATICS AND COMPUTING
A CODES
BORON
C CODES
CALCULATION METHODS
CASMO-2E/PDQ-7E/SIMULATE-E System
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
EDUCATION
ELECTRIC UTILITIES
ELEMENTS
ENRICHED URANIUM REACTORS
EPRI
Electric Power Research Institute (EPRI)
Houston Lighting and Power (HL and P)
MANPOWER
NODAL EXPANSION METHOD
Nuclear Criticality Safety Program (NCSP)
P CODES
PDQ
PHOENIX-P/ANC code
PHYSICS
POWER DENSITY
POWER REACTORS
PUBLIC UTILITIES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
REACTORS
S CODES
SEMIMETALS
SIMULATION
SOUTH TEXAS PROJECT-1 REACTOR
SOUTH TEXAS PROJECT-2 REACTOR
THERMAL REACTORS
TRAINING
WATER COOLED REACTORS
WATER MODERATED REACTORS