Fuel Performance Calculations for FeCrAl Cladding in BWRs
- Univ. of Tennessee, Knoxville, TN (United States). Dept. of Nuclear Engineering
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
This study expands upon previous neutronics analyses of the reactivity impact of alternate cladding concepts in boiling water reactor (BWR) cores and directs focus toward contrasting fuel performance characteristics of FeCrAl cladding against those of traditional Zircaloy. Using neutronics results from a modern version of the 3D nodal simulator NESTLE, linear power histories were generated and supplied to the BISON-CASL code for fuel performance evaluations. BISON-CASL (formerly Peregrine) expands on material libraries implemented in the BISON fuel performance code and the MOOSE framework by providing proprietary material data. By creating material libraries for Zircaloy and FeCrAl cladding, the thermomechanical behavior of the fuel rod (e.g., strains, centerline fuel temperature, and time to gap closure) were investigated and contrasted.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1237610
- Resource Relation:
- Conference: ANS Winter 2015, Washington, DC (United States), 8-12 Nov 2015
- Country of Publication:
- United States
- Language:
- English
Similar Records
BISON Fuel Performance Analysis of FeCrAl cladding with updated properties
Fuel performance analysis of FeCrAl cladding during LWR operation
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ACCIDENT-TOLEANT NUCLEAR FUELS
BWR TYPE REACTORS
FUEL CANS
ZIRCALOY
PERFORMANCE
FUEL RODS
REACTIVITY
STRAINS
TEMPERATURE DISTRIBUTION
IRON BASE ALLOYS
CHROMIUM ALLOYS
ALUMINIUM ALLOYS
TERNARY ALLOY SYSTEMS
COMPARATIVE EVALUATIONS
B CODES
nuclear
nuclear fuel
accident tolerant fuel
ATF
boiling water reactor
BWR
fuel performance
BISON
NESTLE
FeCrAl
cladding
alternate cladding material