skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: PRELIMINARY EVALUATION OF FeCrAl CLADDING AND U-Si FUEL FOR ACCIDENT TOLERANT FUEL CONCEPTS

Conference ·
OSTI ID:1357895

Since the accident at the Fukushima Daiichi Nuclear Power Station, enhancing the accident tolerance of light water reactors (LWRs) has become an important research topic. In particular, the community is actively developing enhanced fuels and cladding for LWRs to improve safety in the event of accidents in the reactor or spent fuel pools. Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system, can tolerate loss of active cooling in the reactor core for a considerably longer time period during design-basis and beyond design-basis events while maintaining or improving the fuel performance during normal operations and operational transients. This paper presents early work in developing thermal and mechanical models for two materials that may have promise: U-Si for fuel, and FeCrAl for cladding. These materials would not necessarily be used together in the same fuel system, but individually have promising characteristics. BISON, the finite element-based fuel performance code in development at Idaho National Laboratory, was used to compare results from normal operation conditions with Zr-4/UO2 behavior. In addition, sensitivity studies are presented for evaluating the relative importance of material parameters such as ductility and thermal conductivity in FeCrAl and U-Si in order to provide guidance on future experiments for these materials.

Research Organization:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
DE-AC07-05ID14517
OSTI ID:
1357895
Report Number(s):
INL/CON-14-33932
Resource Relation:
Conference: Top Fuel - Reactor Fuel Performance, Zurich, Switzerland, September 13–17, 2015
Country of Publication:
United States
Language:
English

Similar Records

Preliminary Evaluation of FeCrAl Cladding for Accident Tolerant Fuel Concepts
Technical Report · Sat Aug 01 00:00:00 EDT 2015 · OSTI ID:1357895

Investigating Accident Tolerant Fuel Concepts using the BISON Fuel Performance Code
Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1357895

Improvements to Modeling Capabilities of ATF Concepts in the BISON Fuel Performance Code
Journal Article · Sat Jul 01 00:00:00 EDT 2017 · Transactions of the American Nuclear Society · OSTI ID:1357895