Basic elements of light water reactor fuel rod design. [FUELROD code]
Basic design techniques and equations are presented to allow students to understand and perform preliminary fuel design for normal reactor conditions. Each of the important design considerations is presented and discussed in detail. These include the interaction between fuel pellets and cladding and the changes in fuel and cladding that occur during the operating lifetime of the fuel. A simple, student-oriented, fuel rod design computer program, called FUELROD, is described. The FUELROD program models the in-pile pellet cladding interaction and allows a realistic exploration of the effect of various design parameters. By use of FUELROD, the student can gain an appreciation of the fuel rod design process. 34 refs.
- Research Organization:
- Univ of Cincinnati, Ohio, USA
- OSTI ID:
- 5341924
- Journal Information:
- Nucl. Technol.; (United States), Vol. 53:3
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of the irradiation behavior of a Zircaloy-4 clad rod containing low density UO/sub 2/ fuel pellets (LWBR Development Program)
Light Water Breeder Reactor fuel element performance characteristics for extending core lifetime: (LWBR Development Program)
Related Subjects
BWR TYPE REACTORS
FUEL RODS
DESIGN
PWR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL CYCLE
FUEL-CLADDING INTERACTIONS
URANIUM DIOXIDE
ZIRCALOY 2
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
FUEL ELEMENTS
IRON ADDITIONS
IRON ALLOYS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled