Fuel performance improvement program. The development of graphite-coated cladding for improved PCI performance of LWR fuels
Description
One of the fuel concepts being tested and demonstrated as part of the Fuel Performance Improvement Program includes a graphite coating applied to the inner surface of the Zircaloy cladding. The technology for producing acceptable coatings was developed starting with the selection of a suitable graphite and culminating with the coating of 200 cladding tubes for demonstration irradiations in the Big Rock Point Reactor. During the process development, methods for controlling the coating thickness and minimizing its hydrogen content were developed that were compatible with production scale operation. During the same period, the graphite coatings were characterized and their properties were determined, mainly to provide information needed for fuel design and licensing considerations. Purity, structure, coating-to-cladding compatibility, thermal conductivity, and friction/wear characteristics were measured
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 42 p.
- Report number
- DOE/ET/34215--15
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12638912
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; FABRICATION; FRICTION; FUEL CANS; FUEL RODS; FUEL-CLADDING INTERACTIONS; GRAPHITE; MICROSTRUCTURE; PWR TYPE REACTORS; SURFACE COATING; THERMAL CONDUCTIVITY; WEAR; ZIRCALOY
- Descriptors DEC
- ALLOYS; CARBON; CRYSTAL STRUCTURE; DEPOSITION; ELEMENTS; FUEL ELEMENTS; NONMETALS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; THERMODYNAMIC PROPERTIES; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- PNL--3541.