Method for Depleting BWRs Using Optimal Control Rod Patterns
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5979781
Control rod (CR) programming is an essential core management activity for boiling water reactors (BWRs). After establishing a core reload design for a BWR, CR programming is performed to develop a sequence of exposure-dependent CR patterns that assure the safe and effective depletion of the core through a reactor cycle. A time-variant target power distribution approach has been assumed in this study. The authors have developed OCTOPUS to implement a new two-step method for designing semioptimal CR programs for BWRs. The optimization procedure of OCTOPUS is based on the method of approximation programming and uses the SIMULATE-E code for nucleonics calculations.
- Research Organization:
- Pennsylvania State University, University Park, PA (United States); Commonwealth Edison (ComEd), Chicago, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5979781
- Report Number(s):
- CONF-910603--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
Similar Records
A two-step method for developing a control rod program for boiling water reactors
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Tue Dec 31 23:00:00 EST 1991
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OSTI ID:5860693
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Journal Article
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OSTI ID:186689
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Conference
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Sat Nov 10 23:00:00 EST 1990
· Transactions of the American Nuclear Society
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OSTI ID:6932875
Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
97 MATHEMATICS AND COMPUTING
BWR TYPE REACTORS
Boiling Water Reactors (BWRs)
CHALCOGENIDES
COMPUTER CODES
CONTROL ELEMENTS
CONTROL SYSTEMS
CRITICALITY
Control Rod (CR) Programming
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
FUEL MANAGEMENT
GADOLINIUM COMPOUNDS
GADOLINIUM OXIDES
IMPLEMENTATION
NONLINEAR PROBLEMS
Nuclear Criticality Safety Program (NCSP)
O CODES
OCTOPUS
OPTIMIZATION
OXIDES
OXYGEN COMPOUNDS
POSITIONING
POWER DENSITY
POWER REACTORS
RARE EARTH COMPOUNDS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTORS
S CODES
SIMULATE-E Code
THERMAL REACTORS
TIME DEPENDENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
97 MATHEMATICS AND COMPUTING
BWR TYPE REACTORS
Boiling Water Reactors (BWRs)
CHALCOGENIDES
COMPUTER CODES
CONTROL ELEMENTS
CONTROL SYSTEMS
CRITICALITY
Control Rod (CR) Programming
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
FUEL MANAGEMENT
GADOLINIUM COMPOUNDS
GADOLINIUM OXIDES
IMPLEMENTATION
NONLINEAR PROBLEMS
Nuclear Criticality Safety Program (NCSP)
O CODES
OCTOPUS
OPTIMIZATION
OXIDES
OXYGEN COMPOUNDS
POSITIONING
POWER DENSITY
POWER REACTORS
RARE EARTH COMPOUNDS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTORS
S CODES
SIMULATE-E Code
THERMAL REACTORS
TIME DEPENDENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS