Development of a reactor engineering workstation at Seabrook station

Conference · Wed Jan 01 00:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7193501

Tremblay, M A; Gorski, J P ^[1]; Gurney, P V ^[2]

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1. Yankee Atomic Electric Co., Bolton, MA (United States)
2. New Hampshire Yankee, Seabrook, NY (United States)

The reactor engineers at Seabrook station are responsible for supporting plant operation with respect to the current reactor core design. Advanced assembly designs, complex reactor core loading patterns, and emphasis on efficient and safe operation puts a greater demand on the reactor engineer. The traditional use of static data constants and coarse core modeling, in light of the more complex fuel and core designs of today, results in less than optimum monitoring and predicting tools for the reactor engineer. The incorporation of an advanced three-dimensional nodal code with thermal feedbacks and detailed spatial modeling along with the ability to follow current operational history on a state-of-the-art workstation provides the reactor engineer with a dynamic core monitoring and predictive tool. This approach allows for more accurate and efficient completion of the reactor engineer's tasks. Yankee Atomic Electric Company (YAEC) is currently in the process of providing advanced reactor physics nodal methods to the reactor engineers at Seabrook station. The scope of this project is to supply a reactor engineering workstation with a simplified user interface to an advanced nodal core model as part of an on-line core monitor/predictor for standard reactor engineering calculations. It uses the Studsvik Core Management System (CMS), which primarily consists of the CASMO-3 cross-section generating code and the SIMULATE-3 three-dimensional two-group nodal reactor analysis code.

• OSTI ID: 7193501
• Report Number(s): CONF-920606-; CODEN: TANSA
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 65; Conference: American Nuclear Society annual meeting, Boston, MA (United States), 7-12 Jun 1992; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR PHYSICS
C CODES
NODAL EXPANSION METHOD
S CODES
SEABROOK-1 REACTOR
REACTOR MONITORING SYSTEMS
ACCURACY
COMPUTER CODES
COMPUTERIZED SIMULATION
DEPARTURE NUCLEATE BOILING
DESIGN
EFFICIENCY
FEEDBACK
FUEL ASSEMBLIES
FUEL MANAGEMENT
HEAT TRANSFER
HYDRAULICS
IN CORE INSTRUMENTS
POWER DENSITY
REACTOR CORES
REACTOR OPERATION
REACTOR SAFETY
REACTOR SHUTDOWN
THREE-DIMENSIONAL CALCULATIONS
BOILING
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
NUCLEATE BOILING
OPERATION
PHASE TRANSFORMATIONS
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR INSTRUMENTATION
REACTORS
SAFETY
SHUTDOWN
SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled