A conceptual design of a fuel bundle for extended burnup in boiling water reactors
A new design concept of a boiling water reactor (BWR) fuel bundle for extended burnup was proposed to improve the capacity factor without increasing the fuel cycle cost. Some effects, which are raised from higher burnup, such as strong pellet-cladding interaction due to enhanced fuel swelling and changes in neutronic characteristics due to increased fuel enrichment, are minimized by a reduction in the maximum fuel temperature to below 1200/sup 0/C and an increase in the moderator-to-fuel ratio. To realize these concepts, a 9 X 9 lattice design with a reduced fuel rod diameter and annular pellets was proposed. The proposed fuel bundle design offers advantages in fuel cycle improvements through extension of achievable burnup and reduction of fuel inventory. The core, loaded with the proposed fuel bundles which achieve 30% higher burnup by the full power month, has a potential for natural uranium savings of about 20% per unit power and a reduction in the amount of reprocessing of about 40% per unit power, compared with the current BWR design when coupled with other improvements such as refueling pattern optimization, natural uranium axial blankets, and spectral shift with flow control.
- Research Organization:
- Hitachi, Ltd., Energy Research Laboratory
- OSTI ID:
- 6291415
- Journal Information:
- Nucl. Technol.; (United States), Vol. 64:1
- Country of Publication:
- United States
- Language:
- English
Similar Records
BWR Fuel-Bundle Extended-Burnup Program: end of Cycle 7 fuel-bundle examination at Monticello Nuclear Generation Plant
Designing fuel rods for high burnup
Related Subjects
BWR TYPE REACTORS
FUEL ELEMENT CLUSTERS
BURNUP
COMPARATIVE EVALUATIONS
DESIGN
COST BENEFIT ANALYSIS
DIMENSIONS
FUEL CYCLE
FUEL-CLADDING INTERACTIONS
MODERATOR-FUEL RATIO
REACTOR LATTICES
FUEL ASSEMBLIES
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled