Utility experience with the BWR power shape monitoring system

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6772119

Emrich, Jr, W J

The Oyster Creek Nuclear Generating Station has used the Electric Power Research Institute (EPRI) boiling water reactor (BWR) power shape monitoring system (PSMS) for approximately one cycle of power operation. During this time, the PSMS was used for both on-line core monitoring and off-line core simulation. The ability to obtain core power distributions in near real time and the ability to simulate anticipated core maneuvers has enabled site personnel to avoid difficult operational situations and to more easily detect problems when they occur. The PSMS is an integrated set of computer codes used to monitor and predict the nuclear and thermal-hydraulic behavior of a BWR code. The PSMS uses a three-dimensional, one-energy-group nodal model similar to the General Electric FLARE code to estimate the core power distribution. The PSMS contains four major modules: (1) data acquisition and storage module: collects plant data; (2) duty cycle approximation module; performs three-dimensional nuclear and thermal-hydraulic calculations; (3) model calibration module: performs all statistical evaluations; and (4) data display module: responsible for displaying PSMS data. The PSMS also has the ability to perform useful predictive calculations. These include: power, flow, or control rod searches; control rod pattern optimizations; and fast approximate predictions.

• Research Organization: GPU Nuclear Corp., Forked River, NJ
• OSTI ID: 6772119
• Report Number(s): CONF-860610-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ACCURACY
BWR TYPE REACTORS
CALIBRATION
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
CONTROL ELEMENTS
DATA ACQUISITION SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EPRI
ERRORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
OPERATION
OYSTER CREEK-1 REACTOR
POWER DENSITY
POWER REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTOR OPERATION
REACTORS
SENSITIVITY
SIMULATION
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS