PWR cladding optimization for enhanced performance margins
- 1. Westinghouse Electric Co., Vaesteras (Sweden)
- 2. Westinghouse Electric Co., Columbia SC (US)
Description
As the nuclear power generating industry has matured there is an increasing trend in core operating fuel duties. This drives a continuing evolution of cladding materials, to provide performance margin and support even higher fuel duty designs. Westinghouse has developed an optimized version of ZIRLOTM, with a thin level reduced from the nominal standard ZIRLO level of 1% to a range of 0.6% to 0.8%. The lower tin level has been shown to reduce the clad corrosion of fuel rods during reactor core operation by 30% or more while still providing the mechanical and off-normal corrosion protection benefits associated with tin alloy additions. Peak oxide levels of only 20-30 μm are observed at burnups up to 63 MWd/kgU. Using relatively small changes in the final annealing temperature, the clad creep can be adjusted to meet target ranges. In-reactor measurements of creep and growth of Optimized ZIRLOTM verify mechanical characteristics equivalent to standard ZIRLO. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [5 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39087323
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; CORROSION PROTECTION; CREEP; FUEL RODS; IRRADIATION; OPTIMIZATION; PERFORMANCE; PWR TYPE REACTORS; RECRYSTALLIZATION; SAFETY MARGINS; TIN; ZIRCALOY
- Descriptors DEC
- ALLOYS; DEPOSITION; ELEMENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MECHANICAL PROPERTIES; METALS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name Final Paper, Paper ID ICONE15-10645.pdf; 2 refs., 4 figs.