Method for generating a control rod program for boiling water reactors
Journal Article
·
· Nucl. Technol., v. 28, no. 1, pp. 108-118
OSTI ID:4101482
The OPROD computer code has been developed to generate a long-term control rod program, a series of control rod patterns that optimize a cycle length within various operational constraints. In the algorithm, the optimization problem is decomposed into two hierarchies. In the inner loop, a time-invariant target power distribution is assumed, and a control rod pattern is determined so as to best fit the power distribution to the target within the constraints at each burnup step. The target is then improved in the outer loop to achieve a longer cycle length. The code consists of two major parts: a three- dimensional boiling water reactor (BWR) core simulator and MAP, the method of approximate programming. It readily generates a long-term control rod program of BWRs without trial search by core-management engineers. The OPROD has therefore facilitated prompt response to varying operating conditions and the investigation of a conflicting relationship between the thermal limitation and the cycle length. (auth)
- Research Organization:
- Atomic Energy Research Lab., Kawasaki, Japan
- NSA Number:
- NSA-33-019403
- OSTI ID:
- 4101482
- Journal Information:
- Nucl. Technol., v. 28, no. 1, pp. 108-118, Journal Name: Nucl. Technol., v. 28, no. 1, pp. 108-118; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
A two-step method for developing a control rod program for boiling water reactors
Boiling water reactor control rod programming using heuristic and mathematical methods
Method for Depleting BWRs Using Optimal Control Rod Patterns
Journal Article
·
Tue Dec 31 23:00:00 EST 1991
· Nuclear Technology; (United States)
·
OSTI ID:5860693
Boiling water reactor control rod programming using heuristic and mathematical methods
Journal Article
·
Mon Mar 31 23:00:00 EST 1980
· Nucl. Technol.; (United States)
·
OSTI ID:7065371
Method for Depleting BWRs Using Optimal Control Rod Patterns
Conference
·
Sun Jun 02 00:00:00 EDT 1991
· Transactions of the American Nuclear Society
·
OSTI ID:5979781
Related Subjects
*BWR TYPE REACTORS-- POWER DISTRIBUTION
*POWER DISTRIBUTION-- OPTIMIZATION
210100* --Nuclear Power Plants--Power Reactors
Non- Breeding
Light-Water Moderated
Boiling Water Cooled
ALGORITHMS
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL ELEMENTS
FUEL MANAGEMENT
MATHEMATICAL MODELS
N77100* --Reactors--Power Reactors
Non-breeding
Light- water Moderated
Boiling Water-cooled
O CODES
*POWER DISTRIBUTION-- OPTIMIZATION
210100* --Nuclear Power Plants--Power Reactors
Non- Breeding
Light-Water Moderated
Boiling Water Cooled
ALGORITHMS
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL ELEMENTS
FUEL MANAGEMENT
MATHEMATICAL MODELS
N77100* --Reactors--Power Reactors
Non-breeding
Light- water Moderated
Boiling Water-cooled
O CODES