Development of SiC-based Cladding for Accident Tolerant Fuels
- 1. Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN, 37831 (United States)
Description
Fuels and core structures in current light water reactors (LWR's) are vulnerable to catastrophic failure in severe accidents. This vulnerability is attributed primarily to the rapid oxidation kinetics of zirconium alloys in a water vapor environment at very high temperatures. Alternative materials to zirconium alloys with reduced oxidation kinetics are sought to enable enhanced accident-tolerant fuels and cores. Among the candidate alternatives, silicon carbide (SiC) - based materials, in particular continuous SiC fiber-reinforced SiC matrix ceramic composites (SiC/SiC composites), are considered to offer outstanding safety benefits. The primary objective of this work is to provide with updated overviews of the concepts, development status, and future prospect for the SiC-based accident-tolerant fuel (ATF) claddings. A systematic technology evaluation program plan was developed and updated to review the technologies needed, to identify and analyze critical gaps, and to lay out a road-map toward establishing key technologies. The technology review and the gap analysis in this exercise were based on an early study and community workshops. Many of the technical gaps identified are related with the three key feasibility issues: hydrothermal corrosion, mechanical failure, and fuel compatibility. Additional performance issues including accident-tolerance features and fission product retention during the normal operation have also been identified. The program plan was designed to systematically address the key gap issues and is formulated in a work breakdown structure. Simultaneously, the plan is being established to set a technical program for advancing the technological readiness levels of concept non-specific essential technologies in three top-level categories of Design and Failure, Environmental Effects, and Off-normal Behavior. The execution of the program plan is in progress across the U.S. Department of Energy laboratories, industries, universities, and international collaborators. The critical issues for SiC composite-based fuel cladding concepts were found to be related to the performance in the normal operation. In particular, radiation-assisted hydrothermal corrosion and the gaseous fission product (FP) retention are identified to be the most critical issues. The primary ORNL concept pursues the use of dual-purpose coating on the SiC composite cladding wall to mitigate the corrosion and the gas permeation issues at the same time, whereas the alternative approaches such as the dense monolithic SiC protective layer combined with the water chemistry control may be feasible. Surface metallization through variations of physical vapor deposition and electroplating are being demonstrated. The FP gas retention is an issue associated with the cracking for the ceramic matrix composite cladding. To establish the probabilistic failure behavior, the relevant test methods were developed in ASTM Committee C28 on Advanced Ceramics. Toward the end-plugging technology development, various methods for joining SiC to SiC had been developed and tested for mechanical properties, irradiation effects, and environmental effects. Multiple methods including the pressureless transient eutectic SiC joining and CVD-based SiC joining were identified particularly promising. In addition, a multi-physics, three-dimensional finite element-based modeling is in progress toward an integrated simulation of the SiC composite-cladded fuel evolutions. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 114
- Journal Issue
- 1
- Journal Page Range
- p. 980
- ISSN
- 0003-018X
Conference
- Title
- Annual Meeting of the American Nuclear Society. Embedded topical meeting 'Nuclear fuels and structural material for the next generation nuclear reactors'
- Dates
- 12-16 Jun 2016
- Place
- New Orleans, LA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52032300
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; CORROSION; ELECTROPLATING; ENVIRONMENTAL EFFECTS; FAILURES; FISSION PRODUCTS; IRRADIATION; MECHANICAL PROPERTIES; PHYSICAL VAPOR DEPOSITION; PROBABILISTIC ESTIMATION; SEVERE ACCIDENTS; SILICON CARBIDES; SIMULATION; WATER CHEMISTRY; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER VAPOR; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACCIDENTS; ALLOYS; BEYOND-DESIGN-BASIS ACCIDENTS; CALCULATION METHODS; CARBIDES; CARBON COMPOUNDS; CHEMICAL REACTIONS; CHEMISTRY; DEPOSITION; ELECTRODEPOSITION; ELECTROLYSIS; ENERGY SOURCES; FLUIDS; FUELS; GASES; ISOTOPES; LYSIS; MATERIALS; NUCLEAR FUELS; PLATING; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SILICON COMPOUNDS; SURFACE COATING; TRANSITION ELEMENT ALLOYS; VAPORS
Optional Information
- Notes
- 4 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States