Surface area considerations for corroding N reactor fuel
Description
The N Reactor fuel is corroding at sites where the Zircaloy cladding was damaged when the fuel was discharged from the reactor. Corroding areas are clearly visible on the fuel stored in open cans in the K East Basin. There is a need to estimate the area of the corroding uranium to analyze aspects of fuel behavior as it is transitioned. from current wet storage to dry storage. In this report, the factors that contribute to open-quotes trueclose quotes surface area are analyzed in terms of what is currently known about the N Reactor fuel. Using observations from a visual examinations of the fuel in the K East wet storage facility, a value for the corroding geometric area is estimated. Based on observations of corroding uranium and surface roughness values for other metals, a surface roughness factor is also estimated and applied to the corroding K East fuel to provide an estimated open-quotes trueclose quotes surface area. While the estimated area may be modified as additional data become available from fuel characterization studies, the estimate provides a basis to assess effects of exposed uranium metal surfaces on fuel behavior in operations involved in transitioning from wet to dry storage, during shipment and staging, conditioning, and dry interim storage
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE96012331; NTIS; US Govt. Printing Office Dep.Files
27068825.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 53 p.
- Report number
- PNNL--11174
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27068825
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- CORROSION; FUEL ELEMENTS; HANFORD PRODUCTION REACTORS; IMAGES; ZIRCALOY
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; PLUTONIUM PRODUCTION REACTORS; PRODUCTION REACTORS; REACTOR COMPONENTS; REACTORS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Contract/Grant/Project number
- Contract AC06-76RL01830
- Funding organization
- USDOE, Washington, DC (United States).