U3Si2-SiC fuel performance analysis in BISON during normal operation
Creators
- 1. Science Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213 (China)
- 2. Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge, MA 02139 (United States)
Description
Highlights: • An empirically-fit thermal-conductivity damage model for SiC composite layer. • U3Si2-SiC fuel performance simulation in BISON under normal operation. • U3Si2 fuel pellet and SiC cladding deformation were compared to UO2 and Zircaloy. - Abstract: U3Si2-SiC is an accident-tolerant fuel concept currently under development by Westinghouse that has potential to improve economic performance and safety of light water reactors. Since U3Si2 fuel suffers from poorer hydrothermal corrosion performance relative to UO2, it is paramount in an U3Si2-SiC fuel rod to lower the stress in the cladding to prevent any inward leakage of coolant. This motivates a detailed fuel-clad analysis of U3Si2-SiC during normal operation. The SiC cladding is modeled with a layer of SiCf/SiC composite followed by a layer of monolithic SiC. The dependence of thermomechanical properties for each SiC layer on temperature and neutron fluence is considered in the BISON fuel performance code. Particularly, pseudo-ductile deformation and anisotropic swelling models of SiCf/SiC composite are updated. While SiC thermal conductivity is commonly known to decrease as a consequence of irradiation damage, its additional degradation by mechanical damage is also modeled. Owing to limited availability of U3Si2 irradiation behavior models and experimental data under power reactor conditions, several assumptions are made to perform the initial detailed assessment of the fuel system. The results show that the fuel rod designs with larger pellet radius, thinner SiC cladding and larger initial gap width (thus larger cladding inner radius) can be beneficial to lower cladding stress during power operation and reactor shutdown.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2019.04.021Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2019.04.021;
- PII
- S0306454919302051;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 132
- Journal Page Range
- p. 34-45
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51007950
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; CLADDING; COMPUTERIZED SIMULATION; COOLANTS; CORROSION; EXPERIMENTAL DATA; FUEL PELLETS; FUEL RODS; LEAKS; NEUTRON FLUENCE; POWER REACTORS; REACTOR SAFETY; REACTOR SHUTDOWN; SILICON CARBIDES; STEADY-STATE CONDITIONS; THERMAL CONDUCTIVITY; URANIUM DIOXIDE; URANIUM SILICIDES; WATER MODERATED REACTORS; ZIRCALOY
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; DATA; DEPOSITION; ENERGY SOURCES; FUEL ELEMENTS; FUELS; INFORMATION; MATERIALS; NUCLEAR FUELS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; PELLETS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SAFETY; SHUTDOWN; SILICIDES; SILICON COMPOUNDS; SIMULATION; SURFACE COATING; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
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